ML20195B480

Rev 20 to ANO QA Manual Operations

ML20195B480
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/07/1998
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20195B447	List: 0CAN119807, Forwards Rev 20 to ANO QA Manual Operations,Per 10CFR50.54(a) & 10CFR50.71(e) ML20195B480
References
NUDOCS 9811160147
Download: ML20195B480 (200)

Text

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i i i ARKANSAS NUCLEAR ONE .

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OUALITY ASSURANCE MANUAL OPERATIONS l l

REVISION 20 ]

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APPROVED: S - d DATE: f[~k"78 SUPERVISOR, QUALITY ASSURANCE APPROVED: ,/ DATE: ((

DIRECTOR, AMSAFETY 7 //

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VIC8PRESIDFfT,6PERATIONS ANO /N l

CONTROLLED SET # /

ENTERGY QA MANUAL OPERATIONS REV. 20 Q OPERATIONS

_ ARKANSAS NUCLEAR ONE SECTION: APPROVAL SIGNATURES COVER PAGE 9811160147 991109I PDR ADOCK 05000313 i P PDR_  !

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,A RECORD OF UPDATES TO REVISION 19 UPDATE NO. PAGE NO. SECTION DESCRIPTION I 1.3.6 Change title from Supervisor, EP to Manager EP 1 1-13 l (Currently Section 1.3.7, Page 1-14) i 2 B-5 ISI Program change to 1992 Code Edition i.

3 2-2 2.2.2 Change wording to allow boric acid to be procured cornmercial grade

! 4 T2-1 Table 2 Add reference to 1000.153 "ER Process" 5 B-5 IST Program change to 1989 Code Edition 6 T2-1 Table 2 Update table references for QA Records 7 TC-1, RU-l Include: " Record of Updates to Revision 19" page 8 3-1, 3-3 3.0 Remove " Plant Mod Procedures" specifically

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4 T3-2 Table 3 9 Various 4.0, 7.0, Address requirements for EOI Shared Services 18.0 10 T2-1 Table 2 Replace Reference to 1000.016 with Reference to 1013.002 11 Various Various Change " Director, Quality" to " Director, Nuclear Safety". Minor reference corrections. Add

" Manager, Nuclear Safety" 12 Various 1.3.1 Organizational Changes F-2, F-3, F-4 AB-3 13 C-4 Terms /Def. Add " Maintenance Action Item" to "Jcb Order" definition.

14 1-6, F-2 1.3.1.3 Add " Manager, Radiation Protec." & " Superintendent,"

Figures Chemistry" 15 Various Various Incorporate all Rev.19 updates into Rev. 20 for submittal to NRC ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS SECTION: (Previous) REVISION UPDATES PAGE RUP-1 ARKANSAS NUCLEAR ONE

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RECORD OF UPDATES TO REVISION 20

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UPDATE NO. PAGE NO. SECTION DESCRIPTION 4

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ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: (Current) REVISION UPDATES PAGE RUC-1 j

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rN TABLE OF CONTENTS SECTION SUBJECT - PAGES APPROVAL COVERSIEET N/A RECORD OF UPDATES (Previous Rev.) RUP-1 RECORD OF UPDATES (Current Rev.) RUC-1 TABLE OF CONTENTS TC-1 to TC-4 POLICY STATEMENT A-1 to A-2 INTRODUCTION B-1 to B-5 TERMS AND DEFINITIONS C-1 to C-9 m 1.0 ORGANIZATION 1-1 to 1-25 2.0 QUALITY ASSURANCE PROGRAM 2-1 to 2-8 .

3.0 DESIGN CONTROL 3-1 to 3-4 4.0 PROCUREMENT DOCUhENT 4-1 to 4-2 CONTROL 5.0 INSTRUCTIONS, PROCEDURES 5-1 to 5-4 AND DRAWINGS 6.0 DOCUMENT CONTROL 6-1 to 6-2 7.0 CONTROL OF PURCHASED 7-1 to 7-6 MATERIAL, EQUIPhENT AND SERVICES l l}

ENTERGY QA MANUAL OPERATIONS REV, 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE OF CONTENTS PAGE TC-1

1 gm 8.0 IDENTIFICATION AND CONTROL 8 1 to 8-3 4

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OF MATERIALS, PARTS AND 4

COMPONENTS 9.0 CONTROL OF SPECIAL 9-1 to 9-2 PROCESSES i

10.0 INSPECTION 10-1 to 10-5

, 11.0 TEST CONTROL 11-1 to 11-4 1

12.0 CONTROL OF MEASURING AND 12-1 to 12-4

TEST EQUIPhENT 13.0 HANDLING, STORAGE AND 13-1 to 13-4 SHIPPING

, 14.0 INSPECTION, TEST AND 14-1 to 14-5 OPERATING STATUS 15.0 NONCONFORMING MATERIAL, 15-1 to 15-4 j PARTS AND COMPONENTS 16.0 CORRECTIVE ACTION 16-1 to 16-3 17.0 QUALITY ASSURANCE RECORDS 17-1 to 17-5 18.0 AUDITS 18-1 to 18-6 FIGURE I ENTERGY OPERATIONS - ANO &

CORPORATE ORGANIZATIONS F-1 FIGURE 2 PLANT OPERATIONS Dl. PARThENT F-2 ENTERGY QA ALOPERATI NS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE OF CONTENTS PAGE TC-2

p FIGURE 4 UNIT 2 OPERATIONS ORGANIZATION F-4 V

FIGURE 5 LICENSING DEPARTMENT F FIGURE 6 SUPPORT DEPARThENT F-6 FIGURE 7 QUALITY DEPARThENT F-7 TABLE 1 ANO EXCEPTIONS / INTERPRETATIONS T1-1 to TI 18 OF REGULATORY GUIDES AND ANSI STANDARDS TABLE 2 QUALITY ASSURANCE T2-1 PROCEDURES MATRIX TABLE 3 QUALITY PROGRAM POLICIES, T3-1 to T3-2 PROCEDURES AND INSTRUCTION MANUALS LIST APPENDIX A . QUALITY PROGRAM FOR AA-1 to AA-4 TRANSPORT PACKAGES APPENDIX B QUALITY PROGRAM FOR AB-1 to AB 11 FIRE PROTECTION APPENDIX C QUALITY PROGRAM FOR AC-1 to AC-3 STATION BLACKOUT C ENTERGY- QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE OF CONTENTS PAGE TC-3

ARKANSAS NUCLEAR ONE POLICY STATEMENT i

QUALITY ASSURANCE PROGRAM FOR OPERATIONS It is the policy at Arkansas Nuclear One, Units 1 & 2 (ANO) and its supporting organizations that the Quality

Assurance Program for Operations (QA Program) meets the requirements of the Code of Federal Regulations, Title 10, Part 50, Appendix B, with respect to operation, maintenance, refueling, repair and modifications, and I

_ inservice inspection. The QA Program shall also meet the requirements of the ASME Boiler and Pressure Vessel Code with respect to items constructed, repaired or replaced to Code requirements.

The Entergy Operations President and Chief Executive Officer has the ultimate responsibility for the safe and reliable operation of the Entergy Operations Nuclear Sites.

2 Under the QA Program, the Vice President. Operations ANO is the final ousite management authority i

responsible for assuring that this policy statement and the QA Program are implemented within ANO. The l Entergy Operations President and Chief Executive OfIlcer; Executive Vice President and Chief Operating Officer; Entergy Operations Vice President, Operations Support; Entergy Operations Vice President, Engineering; and the Director, Human Resources; are responsible for the offsite procedural implementation of p the QA Program within their assigned areas.

b l The General Manager, Plant Operations; Director, Engineering; Director, Nuclear Safety; and Director, Support

are responsible for the daily implementation of the QA Program's procedural requirements at ANO, in their I

respective areas.

The Director, Nuclear Safety is responsible for establishing the QA Program. Responsibility for approval of the QA Program shall be identified within this manual.

Quality personnel reporting to the Director, Nuclear Safety are responsible for auditing the QA Program as necessary and internal inspecting / monitoring activities required by the QA Program to assure compliance with its requirements. Disputes invohing quality, arising from difference of opinions between Quality personnel and l other personnel, which cannot be settled interdepartmentally, shall be presented to the Vice President, i

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Q OPERATIONS ARKANSAS NUCLEAR ONE SECTION: STATEMENT OF POLICY PAGE A-1 1

Operations ANO for resolution. The Director, Nuclear Safety has direct access to the Entergy Operations r' President and Chief Executive Omcer and the Entergy Operations Executive Vice President and Chief Operating V Officer on matters concerning quality.

The Director, Nuclear Safety through the Supenisors, Quality Assurance is to provide for an annual resiew of the adequacy and overall effectiveness of tin QA Program. Any defects in the implementation of either this policy or the QA Program that are revealed during the review are to be reported to appropriate levels of management together with appropriate recommendations.

Implementation of this policy is necessary in order to achieve the reliability and safety required at ANO. Each person involved in actisities concerning ANO is to be responsible for assuring quality in his own work, and for compliance with the requirements of the QA Program. The QA Program policies, manuals, and procedures are mandatory requirements which must be implemented and enforced by all responsible organizations and individuals.

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C. R. Hutchinson Vice President, Operations ANO Date: # '

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ARKA1QA1 NUCLEAR ONE SECTION: STATEMENT OF POLICY PAGE A-2 m

INTRODUCTION l l

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(. This manual describes the Quality Assurance Program for Operations (QA Program) applied to Arkansas Nuclear One, Units 1 & 2 (ANO) and its supporting organizations. This manual is intended to sene as a standard reference for safety analysis reports to fulfill the requirements of the Standard Format and Contents of Safety Analysis Reports for Nuclear Power Plants, Section 17, published by the Nuclear Regulatory Commission.

The objective of the QA Program is to control those phases, as applicable, for the design, procurement, l

l manufacture and fabrication, installation, operation, testing, refueling, repair, maintenance or modification l to existing safety-related (Q-List) stmetures, systems and components that prevent or mitigate the consequences of a postulated accident which may cause undue risk to the health and safety of the public.

The QA Progra is an outgrowth of the principle that quality assurance emanates from each individual contributor and that management is responsible for creating an awareness of quality.

The QA Program is designed to comply with the requirements of 10CFR50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, and also to comply with the quality assurance requirements of the ASME Boiler and Pressure Vessel Code,Section XI for repair, replacement, and insenice inspection ofitems covered by the Code and Licensing commitments.

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The QA Program is also designed to comply with the NRC positicus contained in the following regulatory guides, subject to specific excepdons noted in Table 1 of this manual:

1.8, Rev.1-R Personnel Selection and Training (9n5) 1.28, Rev.1 QA Program Requirements-Design and Construction (3n8) 1.30 QA Requirements for Installation, Inspection and Testing ofInstrumentation and Electrical Equipment (802) 1.33, Rev. 2 QA Program Requirements-Operations (2n8) 1.37 QA Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants (3n3)

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1.38. Rev. 2 QA Requirements for Packaging, Shipping, Receising, Storage and Handling ofitems for Water Cooled Nuclear

.V Power Plants (Sn7) 1.39, Rev. 2 Housekeeping Requirements for Water Cooled Nuclear Power Plants (9n7) 1.58, Rev. ! Qualification of Nuclear Power Plant inspection, Examination and Testing Personnel (9/80) 1.64, Rev. 2 QA Requirements for the Design of Nuclear Power Plants d (6n6) 1.74 QA Terms and Definitions (2n4) 1.88,Rev.2 Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records (10D6) 1.94, Rev.1 QA Requirements for Installation, Inspection and Testing Q of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (406) 1.116, Rev. 0-R QA Requirements for Installation, inspection and Testing of Mechanical Equipment and Senices (6n6) 1.123, Rev.1 QA Requirements for Control of Procurement ofitems and Services For Nuclear Power Plants (7D7) 1.144. Rev.1 Auditing of Quality Assurance Programs for the Nuclear Power Plant (9/80) 1.146 Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (8/80)

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Based upon compliance to these regulatory guides, the QA Program also complies with the following n American National Standards Institute (ANSI) standards subject to exceptions noted in Table 1 of this

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N45.2-1977 Quality Assurance Program Requirements for Nuclear Facilities N45.2.1-1973 Cleaning of Fluid Systems and Associated Components During the Construction Phase of Nuclear Power Plants N45.2.2-1972 Packaging, Shipping, Receiving, Storage and Handling of items for Nuclear Power Plants (During the Construction Phase)

N45.2.3-1973 Househeeping During the Construction Phase of Nuclear Power Plants N45.2.4-1972 Supplementary Quality Assurance Requirements for Installation, inspection and Testing ofInstrumentation and r Electric Equipment During the Construction of Nuclear Power Generating Stations  !

N45.2.5-1974 Supplementary Quality Assurance Requirements for Installation and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants N45.2.6-1978 Qualifications of Inspection, Examination and Testing Personnel for Nuclear Power Plants N45.2.8-1975 Supplementary Quality Assurance Requirements for Installation, inspection and Testing of Mechanical Equipment and System for the Construction Phase of Nuclear Power Plants O ENTERGY QA MANUAL OPERATIONS REV. 20

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N45.2.9-1974 Requirements for Collection, Storage and Maintenance of fs Quality Assurance Records for Nuclear Power Plants V)

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N45.2.10-1973 Quality Assurance Terms and Definitions N45.2.11-1974 Quality Assurance Requirements for the Design of Nuclear Power Plants E

N45.2.12-1977 Requiret. nts for Auditing of Quality Assurance Programs for Nuclear 1-cwer Plants N45.2.13-1976 Quality Assurance Requirements for Control of Procurement ofItems and Senices for Nuclear Power Plants N45.2.23-1978 . Qualification of Quality Assurance Program Audit Personnel for Nuclear Facilities N18.1-1971 Selection and Training of Nuclear Power Plant Personnel

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N18.7-1976 Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants N3.1-1981 Selection, Qualification, and Training of Personnel for Nuclear Power Plants NQA-1-1983 Quality Assurance Program Requirements for Nuclear Facilities The above requirements are implemented by controlling activities as described in this manual and by procedures referenced in this manual.

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The following codes and standards are also utilized within the QA program as applicable to those activities to which they are referenced within various sections of this manual:

D d ASME Section III, Division 1 - 1989 Edition, No Addenda

• ASME Boiler and Pressure Vessel Code - Nuclear Power Plant Components

. ASME Section XI-ISI and IST: 1986 Edition, No Addenda (ANO Unit 2)**

ISI: 1992 Edition with the following portions of the 1993 Addenda (Table IWA-5210-1; Paragraph IWA-5250 (a); paragraph IWA-5265 (b); Table IWB-2500-1, Examination Categories B-E and B-P; Article IWB-5000; Table IWC-2500-1, Examination Category C-H; Article IWC-5000; Article IWD-5000) and the 1980 Edition through Winter 1981 Addenda for ultrasonic examination requirements only. (ANO Unit 1)

IST: 1989 Edition, No Addenda (ANO Unit 1)

ASME Boiler and Pressure Vessel Code - Rules for Inservice Inspection of Nuclear Power Plant Components ASNT SNT-TC-1 A-1984 (Endorsed thru ASME Code Case N-445, dated $/7/87)

Recommended Practice for Nondestructive Testing Personnel Qualification and Certification (This edition shall be used in lieu of earlier editions that rnight be referenced in other codes or standards to which ANO is committed).

Q AWS DI.1-1992 American Welding Society Structural Steel Welding Code In lieu of the original Construction Code, all or portions oflater edtiorsaddenda of the Code (through the 1989 edition) may be specified for repair or replacement (inclumng system changes) of components or systems, within the rules of ASME Section XI. Iflater editions / addenda are selected, design, fabrication, and examination requirements shall be reconciled with the Owner's specification.

Repair / replacement activities shall be to the 1992 Edition with the following portions of the 1993 Addenda (Table IWA-5210-1; Paragraph IWA-5250 (a);

Paragraph IWA-5265(b); Table IWB-2500-1, Examination Categories B-E and B-P; Article IWB-5000; Table IWC-2500-1, Examination Category C-H; Article IWC-5000; Article IWD-5000) and the 1980 Edition through Winter 1981 Addenda for ultrasonic examination requirements only.

Definitions of terms applicable to the QA Program are found in the Terms and Definitions section of this manual.

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TERMS AND DEFINITIONS

-Q (j The terms used in this manual follow the definitions provided in ANSI N45.2.101973, supplemented by additional terms and definitions applicable to this manual.

Approval - An act of endorsing or adding positive authorization. er hoth.

i Appurtenance - A part that is attached to a component which has been completed.

As-Built-Data - Documented data that describes the condition actually achieved in a product.

Assembly - A combination of subassemblies or components, or both, fitted together to form a unit.

Audit - An activity to determine through investigation, the adequacy of and adhere.ne to, established procedures, instructions, specifications, codes, and standards or other applicable cotaractual and licensing requirements, and the effectiveness ofimplementation.

Basic Component - A nuclear plant structure, system or component necessary to assure the nuclear safety criteria.

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Bid Evaluation - A formal evaluation of all proposals received in response to an inquiry to determine the vendor to whom the purchase order will be awarded.

Certificate of Conformance - A written statement, signed by a qualified party, certifying that items or senices comply with specific requirements.

1 Certificate of Compliance - A written statement, signed by a qualified party, attesting that the items or senices are in accordance with specified requirements and accompanied by additional information to 1 l

substantiate the statement.

Certified Test Report - A written and signed document, approved by a qualified party, that contains sufficient data and information to verify the actual properties of items and the actual results of all required tests, d ENTERGY QA MANUAL OPERATIONS REV. 20 Q~ OPERATIONS '

ARKANSAS NUCLEAR ONE SECTION: TERMS AND DEFINITIONS PAGE C-1 l

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Certification - The action of determining, verifying and attesting, in writing, to the qualiDcations of personnel or material.

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Characteristic - Any property or attribute of an item, process, or senice that is distinct, describable, and measurable, as conforming or nonconforming to specified quality requirements. Quality characteristics are generally identiDed in specifications and drawings which describe the item, process, or senice.

Checks - The tests, measurements, verifications or controls placed on an actisity by means of investigations, comparisons, or examinadons, to determine satisfactory conditions, accuracy, safety or performance, Cleanness - A state of being clean in accordance with predetermined standards, and usually implies freedom from dirt, scale, heavy rust, oil or other contaminating impurities.

Code Inspector - A qualified nuclear inspector (ANI or ANII) employed by a legally constituted agency of a Municipality or State of the United States, or Canadian Province, or regularly employ ,d by an Authorized Inspection Agency and having authorized jurisdiction at the site of manufacture for installation, repair, modification, and insenice inspection of ASME Boiler and Pressure Vessel items designated safety-rele:d.

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D Commercial-Grade - A structure, system, or component, or part thereof that affects its safety function, that was not designed and manufactured as a basic component. Commercial grade items do not include items where the design and mamtfacturing process require in-process inspections and verifications to ensure that defects or failures to comply are identified and corrected (i.e., one or more critical characteristics of the item cannot be verified).

Component - A piece of equipment such as a vessel, piping, pump, valve or core support structure, which will be combined with other components to form an assembly.

Computer Code - The application software utilized within a digital computer to accomplish a specific function or task. Computer codes requiring quality assmance are those whose satisfactory performance is  :

I required to prevent accidents which may cause undue risk to the health and safety of the public or relied J upon to mitigate the consequences of such accidents if they were to occur. This involves those computer p ENTERGY QA MANUAL OPERATIONS REV. 20

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codes utilized in design and analyses of Q-list components, and those utilized as an active portion of Q-list

,, components.

Contaminams - Foreign materials such as mill scale, dirt, oil, chemicals and any matter than renders a fluid,' solid or surface impure and unclean according to preset standards of acceptable cleanness.

Contractor - Any organization under contract for furnishing items or senices. It includes the terms Vendor, Supplier, Subcontractor, Fabricator and sub-tier levels of these where appropriate.

Dedication - Designating a commercial-grade item for use as a basic component after receipt. This implies that all required inspections, examinations, testing, and documentation are completed to assure compliance with the Procurement Documents.

Defective Material - A material or component which has one or more ch acteristics that do not comply with specified requirements.

Deviation - A nonconformance or departure of a characteristic from specified requirements.

Documentation - Any written or pictorial information describing, defining, specifying, reporting or

,Q Q certifying activities, requirements, procedures, or results.

Examination - An element ofinspection consisting ofinvestigation of materials, components, supplies or senices to determine conformance to those specified requirements which can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gaging, and measurement.

F-List - A list of Non-Q fire protection equipment within die scope of the " Quality Program for Fire Protection" (Appendix B) - that is, those fire protection and detection systems, and those structures and components (such as fire doors, fire dampers, and penetration seals) which, as identified in the plant's fire hazards analysis report, are required to restrict the damage caused by a single exposure fire to safety-related equipment and equipment required to achieve and maintain safe plant shutdown to within those limits set forth in Section I of Appendix R to 10CFR50. This list is maintained current in the SIMS computer data base.

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Ilandling -An act of physically mosing items by hand or mechanical means, but not including transport modes.

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Inauirv -A document that contains the necessary information for a vendor to make a proposal. An inquiry may include specifications pertaining to the equipment, materials or services proposed to be procured.

Inspector (Owner's)-A qualified inspector employed by the Owner whose duties include the verification of quality-elated activities or installations or both.

Insocction -A phase of quality control which by means of examination, observation or measurement determines the conformance of materials, supplies, components, parts, appurtenances, systems, processes or structures to predetermined quality requirements. I Item -Any level of unit assembly, including structure, system, subsystem, subassembly, component, pan or material.

Job Order (J.O.) or Maintenance Action Item (MAI) - The document used for identifying and administratively controlling the work effort on station equipment and systems. It identifies applicable procedures and drawings; documents reviews, approvals and results ofinspections and tests; and pro > ides e i ty - a mechanism for planning, scheduling and authorizing work.

Manufacturer - One who constructs any class of component, part, or appurtenance to meet prescribed design requirements.

Material - A substance or combination of substances forming components, parts, pieces and equipment items. (Intended to include such as machinery, castings, liquids, formed steel shapes, aggregates, and cement.)

Measurine and Test Eauipment (M&TE) - Devices or systems used to calibrate, measure, gage, test, inspect or control in order to acquire research, development, test or operational data, or to determine compliance with design, specifications or other technical requirements. M&TE does not include permanently installed operating equipment, nor test equipment used for preliminary checks where data obtained will not be used to determine acceptability or be the basis for design or engineering evaluation.

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. Modific" tion - A planned change in plant design or operation and accomplished in accordance with the requirements and limitations of applicable codes, standards, specifications, licenses and predetermined

( . safety restrictions.

Nonconformance - A deficiency in characteristic, document or procedure which renders the quality of an item unacceptable or indeterminent. Examples of nonconformances include: Physical defects, test faihtres, incorrect or inadequate documentation or deviation from prescribed processing, inspection or test procedures.

Nuclear Safety Criteria - (1) Integrity of the reactor coolant pressure boundary; (2) capability to shutdown the reactor and maintain it in a safe shutdown condition; and (3) capability to prevent or mitigate the consequences of accidents which could result in potential off-site exposures comparable to those referred i to in 10CFR100.11.

Objective Evidence - Any statement of fact. information or record, either quantitative or qualitative, pertaining to the quality of an item or senice based on observations, measurements or tests which can be

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verified.

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Operation - The total of administrative, maintenance and monitoring activities necessary to sustain the ,

i power-generating capabilities of the plant after initial start-up.

Owner - The person, group, company or corporation who has title to the facility or installation.

Packace - A wrapping or container including its contents of materials or equipment.

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Packaned Unit - An assembly ofitems and parts which can be disassembled without destroying the integrity of the individual parts. I l

P_ an - An item which has work performed on it and which is attached to and becomes part of a component before completion of the component.

Plant - The equipment, piping, structures, buildings and property that comprise an installation or facility.

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Precedure - A document that specifies or describes how an activity is to be performed. It may include methods to be employed, equipment or materials to be used and sequence of operations.

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Procurement Documents - Contractually binding documents that identify and derme the requirements that

^ items or senices must meet in order to be considered acceptable by the purchaser.

Project - A planned series of activities including all actions necessary to provide, utilize, and maintain a facility or portion thereof.

Proposal - A bid, usually written by a vendor in response to an inquiry, which provides the issuing party with the vendor's proposed compliance to the inquiry and the cost.

Purchase Order (or Contract)- A document authorizing a vendor to provide equipment, material or services in accordance with stated terms and conditions.

Purchaser - The organization or organizations responsible for issuance and administration of a contract, subcontract or purchase order.

O-List - A list of safety-related structures, systems, and components - that is, those structures, systems and Q components that must remain functional during and following design basis events to ensure that the Nuclear Safety Criteria are satisfied.

Oualification (Personnel) - The characteristics or abilities gained through training or experience or both that enable an individual to perform a required function.

Qualified Party - A person or organization competent and recognized as knowledgeable to perform certain functions.

Qualified Proceduce - A procedure which incorporates all applicable codes and standards, manufacturer's parameters, and engineering specifications and has been proven adequate for its intended purpose.

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Q'talified Suppliers List - A listing of vendors having < quality assurance programs consistent with the requirements of applicable portions of 10CFR50, Appendix B. For vendors supplying AShE Code items, (v) they shall also have a quality program consistent with the requirements of applicable portions of AShE Section !!I, Division 1, subsection NCA Quality Assurance - All those planned and systematic actions necessary to provide adequate confidence that an item or a facility will perform satisfactorily in service.

Quality Control - Those quality assurance actions which provide a means to control and measure the characteristics of an item, process or facility to established requirements.

Receiving - Taking delivery of an item at a designated location.

Repair - The process of restoring a nonconforming characteristic to a condition such that the capability of an item to function reliably and safely is unimpaired, even though that item still may not conform to the original requirement.

Report - Something (document) that gives information for record purposes.

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Review - An element of inspection to determine conformance to specified requirements, which can be s

6termined by examination of documents and activities.

l Rework - The process by which a nonconforming item is made to conform to a prior specified requirement by completion, remachining, reassembling or other corrective means.

S-List - A list of non-Q, non-F Components subject to one or more of the QA Program requirements of 10CFR50, Appendix B. This list is maintained current in the SIMS Computer Data Base.

4 Safety-Related (Q) - Safety-related structures, systems and components are those that must remain functional during and following design basis events to ensure that the Nuclear Safety Criteria are satisfied.

Source Surveillance - A review, observation or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procurement or manufacture.

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Specification - A concise stttement of a set of requircraents to be satisfied by a product, material or process indicating, whenever appropriate, the pradure by means of which it may be determined whether p

(j the requirements given are satisfied.

Standard - The result of a particular standardization effort approved by a recognized authority.

Storage - The act of holding items at the constmction site or in an area other than its pennanent location in the plant.

Subsystem - A group of assemblies or components or both combined to perform a single function.

Surveillance - The continuing analysis and evaluz : d records, methods and procedures, including the l act of verification, to assure conformance with technical requirements.

System - A group of subsystems united by some interaction or interdependence, performing many duties but functioning as a single unit. I i

i System Level Design Bases - Information u hich identifies the specific functions to be performed by a l

system and the specific values or ranges of values chosen for controlling parameters as reference bounds _

for design. These values may be (1) restraints derived from generally accepted " state of the att" practices for achieving functional goals, or (2) requirements derived from analysis (based on calculation and/or experiments) of the effects of a postulated accident for which a system must meet its functional goals.

System level design bases include information identifying specific functions to be performed by stmetures with system level functions (e.g., containment building). Information identifying the specific functions to be performed by individual components, component arrangements and structures within a system that do not affect the overall system functions and controlling parameters are not part of the system level design bases.

System Performance Test - A test perfonned on a completed system including electric, instrumentation, controls, fluid and mechanical subsystems under normal or simulated normal process conditions such as temperature, flow, level, and pressure.

Testing- The determination or verification of the capability of an item to meet specified requirements by subjecting the item to a set of physical, chemical, emironmental or operating conditions.

ENTERGY QA MANUAL OPERATIONS REV. 20

!,])

/

OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TERMS AND DEFINITIONS PAGE C-8

Titles - Titles ofindividuals such as Director, Nuclear Safety when used in this manual, assign the responsibility of performing the requirement to the noted individuals or their appointed designees.

I V

Transit - The state of being conveyed or transported from one place to another.

Transit Carrier (Open) - Trucks, trailers, railroad cars, barges, aircraft or ships which do not afford items protection from the environment.

Transit Carrier (Closed) - Trucks, trailers, railroad cars, barges, aircraft or ships which provide protection ofitems from the emironment by nature of their closed design.

Use-As-Is - A disposition which may be imposed for a nonconformance when it can be established that the discrepancy will result in no adverse conditions and that the item under consideration will continue to meet all engineering functional requirements includmg performance, maintainability, fit and safety.

Vendor - Any organization under contract for furnishing items or senices. It includes the terms Contractor, Subcontractor, Supplier, Fabricator and sub-tier levels of these where appropriate.

Verification - An act of confirming, substantiating and assuring that an activity or condition has been implemented in conformance with the specified requirements.

Work Instructions - Written instructions used to transmit detailed information on the specific measures necessary to comply with the requirements of quality assurance procedures or any complex or diff. cult quality-related task.

Work Package - A collection of applicable documents, such as procedures, cleanliness control forms, inspection and test forms, hold card forms, Ignition Source Pennits, drawings, technical manuals, etc.,

needed to perform thejob.

ENTERGY QA MANUAL OPERATIONS REV. 20 t / OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TERMS AND DEFINITIONS PAGE C-9

4 1

1,0 ORGANIZATION O

1.1 SCOPE

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This section describes the Nuclear Organizational structure and responsibilities for establishing and executing the Q A Program for Arkansas Nuclear One, Units 1 & 2 (ANO) in compliance with 10CFR$0, Appendix B and applicable licensing commitments identified in the Introduction. It also includes a description of the interfaces with other organizations which may be delegated the work of establishing and executing portions of the QA Program. The Entergy Arkansas Inc. and Entergy Operations, Inc. (EOI)

Corporate Organizations relevant to the operation of ANO are shown in Figure 1.

1.2 GENERAL RESPONSIBILITIES The on-site, .esponsibility for ANO, including quality assurance, lies with the Vice President, Operations ANO. He provides management assessment of the QA Program through review of reports generated by the Quality Organization and reports of NRC actitities.

13 NUCLEAR ORGANIZATION The Nuclear Organization, headed by the Vice President, Operations ANO is responsible for activities related to the operation of ANO. These activities include as a minimum: design, operation, maintenance, inservice inspection and test, modification and those additional activities discussed in Sections 2.0 through 18.0 of this manual. The Vice President, Operations ANO, who reports to the Entergy Operations Executive Vice President and Chief Operating Officer, is responsible for the formulation, licensing, implementation and discharge of operating policies and procedures relative to nuclear plant operations, nuclear quality and training. The Nuclear Organization is shown in Figures 1 through 8. The Vice President, Operation ANO's duties include the following:

O ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-1

.. ._ _. . _- _ _ . - _ _ _ ~ . . . _ - . . _ _ _ _ _. _ _ . . - ..

(1). , Providing technical direction and administrative guidance to the: I

7 .

{Q a.

b.

General Manager, Plant Operations Director, Nuclear Safety l

c. Director, Support

d. ' Director, Training & Emergency Planning

c. Manager, Modifications

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1 (2) Providing priority of engineering tasks to the Director, l

Engineering (3) Ensuring conformance to the QA Program by instituting the necessary procedures and instructions within the Nuclear Organization (4) Providing for review and approval of design and engineering performed for ANO l

(5) - Providing for review and approval of procurement documents for equipment, material and l services l

i

^ /} -(6) Providing for liaison between ANO and applicable regulatory agencies l

(7) Providing and maintaining a qualified and suitable staff to carry out required departmental functions iI (8) Assuming overall responsibility for the fire protection, emergency planning and radiation protection programs implemented at ANO (9) Implementing the Entergy Operations, Inc. Welding Program b'

ENTERGY QA MANUAL OPERATIONS REV, 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-2

1.3.1 General Manager. Plant Operations (n

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L The General Manager, Plant Operations reports to the Vice President, Operations ANO and has direct responsibility for operating ANO in a safe, reliable and efficient manner. He is responsible for operating ANO in accordance with the provisions of the operating licenses. The Operations Depanment's organization is shown in Figure 2. The General Manager, Plant Operations has the authority to shut down either unit if required. The General Manager, Plant Operations provides technical direction and administrative guidance to the:

i (1) Plant Manzger, Unit I (2) Plant Manager, Unit 2 (3) Manager, Radiation Protection / Chemistry.

(4). Manager, Standards (5) Manager, Outage and Work Management In addition, the General Manager, Plant Operations provides planning, direction, control and overall supervision to the Safety section in operating and maintaining ANO.

1.3.1.1 Plant Managers, Unit 1 & 2 ' i (D

LJ The Plant Managers, Unit 1 & 2 report to the General Manager, Plant Operations and are responsible for the actual operation of their assigned nuclear unit, the maintenance of plant equipment and facilities and the planning / scheduling of plant work activities. The Units' Operations organizations are shown in Figures 3 and 4. The Plant Managers, Unit-1 & 2 provide technical direction and administrative guidance to:

- (1) Manager, Operations, Unit 1 & 2 (2) Manager, Maintenance, Unit-1 & 2 (3) Project Manager, Outages, Unit-1 & 2 *

(4) Manager, System Engineering, Unit-1 & 2

• Matrix position from Manager Outage and Work Management.

t

'V ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-3

1.3.1.1.1 p

! The Managers, Operations, Unit-1 & 2 are responsible for directing the actual day-to-day operations of their assigned unit. They supenise each unit's operating staff and interface with the respective Managers, Maintenance, Unit-1 & 2 to accomplish opera %on-related maintenance activities. They are responsible for coordination of the daily resiew of operating surveillance tests and coordination of operation-related maintenance activities. The Managers, Operations, Unit-1 & 2 are also responsible for supenision of core refueling, which includes advance planning for the outage, plant preparation, equipment checkout and the refueling operations. The Managers, Operations each hold an NRC Senior Reactor Operator License. The Managers, Operations, Unit-1 & 2 provide technical direction and administrative guidance to the Superintendents, Shift Operations of their assigned unit.

j 1.3.1.1.1.1 The Superintendents, Shift Operations report to the applicable Manager, Operations and are responsible for the actual operation of the unit and for the activities of the Operators during their assigned stdfts. The Superintendent, Shift Operations is cognizant of operation activities being performed while on duty. The  !

Superintendent, Shift Operations on duty has the authority to shut down the unit if, in Idsjudgment, conditions warrant such action. The Superintendents, Shift Operations each hold an active Senior Reactor Operator License. The Superintendents, Shift Operations provide technical direction and administrative guidance to the:

(1) Control Room Supenisors (Holders of active Senior Reactor j Operator License)

(2) Sidft Engineers (3) Control Board Operators (Holders of active Reactor Operator License)

(4) Waste Control Operators (5) Auxiliary Operators ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCL. EAR ONE SECTION: 1.0 ORGANIZATION PAGE l-4

. _ ._._. . . _ . . _ . _ . ._ _ _ . . _ . . _ . . _ _ _m . __ _ .

1.3.1.1.2 p

( The Managers, Maintenance, Unit-1 & 2 report to the applicable Plant Manager and are responsible for the maintenance of plant equipment and facilities as defined by plant maintenance program implementing procedures and ensuring that maintenance of equipment is performed in cempliance with applicable standards, codes, specifications and procedures. The Managers, Maintenance have responsibility for activities common to Unit I and Unit 2. The Managers, Maintenance, Unit 1 & 2 also coordinate operation-related maintenance activities with the applicable Managers, Operations, Unit-1 & 2 and are responsible to make repairs on any stmeture, system or component under their control.

1.3.1.1.3 The Project Managers, Outages Unit-1 & 2 report to the Manager, Outage and Work Management in administrative matters and to the Plant Manager Unit 1 & 2 respectively, on matters related to specific plant outage activities.

1.3.1.1.4 The Managers, System Engineering, Unit-1 & 2, report to the applicable Plant Manager and are responsible for reactor, performance, and system engineering activities required for the safe and efficient production of electricity. These activities include resching plant related engineering issues that do not alter the system level design bases of the respective plants.

1.3.1.1.5 The planning and scheduling of plant work activities are executed under the ANO Plant Manager for Unit 1 & 2, respectively. The unit outage manager reports to the respective unit plant manager and is responsible for scheduling outage and non-outage work activities for that unit, supenising the scheduling stafT, and interfacing with the respective unit maintenance manager, who has responsibility for planning and execution of plant work acthities.

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-5

1.33.2 Manager, Standards 7 . The Manager, Standards reports to the General Manager, Plant Operations and provides planning, x ..

direction, control and overall supenision to the Standards Department. Responsibilities also involve the +

Chairpersonship of the Plant Safety Committee which reviews the various aspects of operation, maintenance, modification and support to assure the safety of ANO. Responsibilities involve the

. supervision of personnel and daily work activities involving the safe, efficient and reliable operation of s

ANO. Responsibilities involve the development and administration of programs which support the  ;

capability of ANO to meet or exceed industy standards and regulatory requirements.  ;

n 1.3.1.3 Manager, Radiation Protection / Chemistry  ;

4 4 The. Manager, Radiation Protection / Chemistry reports to the General Manager, Plant Operations and is

, responsible for implementing the Nuclear Orga azahn chemistry, radiation protection programs. The f Manager, Radiation Protection / Chemistry, provides technical direction and administrative guidance to:

(1) Manager, Radiation Protection (2) Superintendent, Chemistry.

1.3.1.3.1 The Manager, Radiation Protection meets the Reg. Guide 1.8 requirements for RPM and is directly responsible for implementation of the radiation protection and health physics policies, programs, and procedures. As such the Manager, Radiation Protection is responsible for implementing controls which will minimize personnel radiation exposure (ALARA), minimize personnel contamination, minimize radwaste volume, and establish uniform procedures and methods for contamination control and radiation g- protection. The Manager, Radiation Protection reports to the Manager, Radiation Protection /Chemisty in administrative matters and routine radiation protection and radwaste concerns and to the Vice President.

( Operations in matters of radiological health and safety policy.

1.3.1.3.2 The Superintendent, Chemistry is responsible for implementing programs, policies and procedures as required to maintain chemistry and radiochemistry parameters in specification. In addition, the Superintendent, Chemistry is responsible for establishing and maintaining chemistry and radiochemistry controls that are conductive to maximizing plant life.

1.3.1.4 Manager, Outage and Work Management The Manager, Outage and Work Management has overall responsibility for developing and maintaining processes and programs for managing outages and workload at ANO. This position staffs and provides oversite of planning, scheduling and supervisory resources for same to support the ANO operating units.

Primary focus is on the consistent prioritization, planning and scheduline nf on h ne and outage project and work activities.

' This position provides technical and administrative guidance to the:

Project Manager Outages, Unit 1 Project Manager Outages, Unit 2 REV. 20

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ENTERGY QA MANUAL OPERATIONS OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l6

- - - . ~. ~.. . . . .. -- . . .- .. _ -.

Supenisor, ANO Planning -

Project Manager, Refueling P 1.3.2 Director. Nuclear Safety 1.3.2.1 The Director, Nuclear Safety reports to the Vice President, Operatiora ANO and has overall responsibility for the management and oversight of NRC inspection activities, industry and in-house operation experiences, safety assessments, and interactions with the NRC regional and Washington, DC ofIices. The Licensing Department's organization is shown on Figure 5.

The Director, Nuclear Safety provides technical direction and administrative guidance to the:

(1) Supenisor, Licensing - Region (2) Supenisor, Licensing - NRR (3) Supenisor, Industry Events Analysis (4) Supenisor,in-House Events Analysis and Assessment (5) Manager, Nuclear Safety f~% 1.3.2.1.1 Supenisor, Licensing - Region

(. l The Supenisor, Licensing - Region reports to the Manager, Nuclear Safety and is responsible for the following duties:

(1) Interfacing with on-site and regional regulatory agencies and the Director, Nuclear Safety pertaining to Licensing and regulatory matters (2) Establishing and maintaining a system for monitoring Licensee Event Reports and NRC Inspection Reports l

1 (3) Performing SAR updates (4) Providing te.chnical direction and administrative guidance to the Licensing Specialists 1.3.2.1.2 Supenisor, Licensing-NRR

()

* / ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-7

. . - . . - - - .. . . ~ . . _ . - . - - - - - . . - - .- - . - . - - .~.

The Supenisor, Licensing-NRR reports to the Manager, Nuclear Safety and is responsible for the following duties:

(1) Interfacing with NRC, Washington, DC offices and the Director. Nuclear Safety pertaining to Licensing and regulato:y matters (2) _ Establishing and maintaining programs for the maintenance of L icensing Base Documents

. (Operating License, SAR, Technical Specification, Emergency Plan, QA Manual

_ Operations) with the assistance of other department's expertise -

,. (3) Responding to Generic Letters and Bulletins (4) Reviewing NRC Correspondence (incoming and outgoing) and related industry documents to remain cognizant of activities that may affect ANO

_ (5) Providing evaluations and recommendations in meeting regulatory commitments (6) Providing technical direction and administrative guidance to the Licensing Specialists -

~ 1.3.2.1.3 Supeniscr, Industry Events Analysis The Supenisor, Industry Events Analysis reports to the Manager, Nuclear Safety and obsenes the nuclear industry for indicators and lessons learned which can be of use to correct existing ANO problems or to avoid problems others have experienced. The section assesses applicability of current industry issues to ANO and develops proposed action plans for consideration and implementation by line management.

Inputs to this function are SOERs, SERs, O&MRs, SEE-IN documents, NRC Informat.an Notices and vendor notifications (including 10CFR21 reports). Additionally, this section is the interface for reporting to Nuclear Network concerning events that occur at ANO.

' l.3.2.1.4 - Supenisor,In-House Events Analysis and Assessment The Supenisor, In-House Events Analysis and Assessment reports to the Manager, Nuclear Safety and has the responsibility for administration of ANO's pnmary corrective action program, the Condition Reporting System. This responsibility includes:

ENTERGY_ QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-8

(1) Reviewing identified conditions adverse to quality in order to recommend appropriate

,,s dispositions to plant management l

( (2) Assisting in the performance of root cause determinations to ensure their adequacy (3) Reviewing the actions taken to resolve conditions and taking action to ensure resolution of the condition (4) Maintaining a tracking system and reporting mechanism for identified conditions Additionally, the Supenisor, In-House Events Analysis and Assessment is responsible for providing assessments of plant and industry operating experiences, oversight of plant experiences, oversight of selected key station programs, and assisting station management in monitoring and evaluating ANO performance to ensure that effective management programs are developed, implemented and maintained to achieve the goals and Standards of Excellence as prescribed by senior management. This responsibility is accomplished through a variety of methods including: evaluating plant programs or functional areas, independent investigations of selected plant events or conditions, and a periodic assessment of overall plant activities. The In-House Events Analysis and Assessment section provides independent, objective assessments (outside the traditional auditing role) of the overall effectiveness of nuclear programs to help assure that performance expectations are being met. The inputs to this process include the assessment of i

prior and current ANO performance contrasted against, comparable industry performance, the Standards of Excellence identified by INPO, and the evaluation ofindustry strengths and good practices foi applicability y) to ANO, and other applicable nuclear industry requirements. The Supervisor, in-House Events Analysis and Assessment manages the plant operation experience review program in accordance with INPO guidelines.

1.3.2.2 The Director, Nuclear Safety also has overall responsibility for the Quality Organization which performs reviews, analysis, surveillance, inspection, nondestructis e examination and audit functions during the operational phase of ANO. The Quality Organization is also independent of plant operations and has sufficient independence from cost and schedule when opposed to safety considerations. The Director,

• Nuclear Safety has direct access to all management levels, which assures his staff the ability to: identify quality problems; initiate, recommend or provide solutions through designated channels; and verify implementation of solutions. The Quality Department's Organization is shown on Figure 7.

A f i ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-9

l The Director, Nuclear Safety presides technical and administrative guidance to:

o (1) Coordinator, Quality

(' 2) - Supenisor(s), Quality Assurance (3) Supenisor, Quality Control

-(4) Supenisor, NDE Duties and responsibilities of the Director, Nuclear Safety include the following:

(1) Technical direction, administrative guidance and supenision to the Coordinator, Quality; Supenisor(s), Quality Assurance; Supenisor, Quality Control; and Supenisor NDE (2) Approval of the QA Manual Operations and revisions thereto (3) Approval of QA/QC and NDE procedures and revisions thereto as established within Quality procedures 1.3.2.2.1 Coordinator. Quality The Coordinator, Quality reports to the Director, Nuclear Safety. Duties and responsibilities of the Coordinator, Quality include assisting the Director, Nuclear Safety with ha duties and responsibilities.

1.3.2.2.2 Supervisor (s), Quality Assurance The Supenisor(s), Quality Assurance reports to the Director, Nuclear Safety. Duties and responsibilities of the Supenisor(s), Quality Assurance include the following:

(}) Developing the QA Program requirements for operation, maintenance, and modification activities related to safety-related (Q-listed) systems, structures and components (2) Auditing of the quality activities as described in Section 18.0 of this manual (3) Providing to the Director, Nuclear Safety, on an annual basis, the results of a resiew of the QA Program to determine the effectiveness and proper implementation of the QA Program f

\

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-10

(4) Authority to stop work where conditions exist that prohibit effective quality programs, or if faulty materials, incorrect workmanship or procedures are detected O (5) Ensuring approval and control of quality assurance programs for outside organizations

, panicipating in the QA Program (6) Providing and maintaining a qualified and suitably trained stafito carry out required staff functions (7) Formulating programs for maintaining the professional competence of personnel within the Quality Assurance section and providing assistance in Quality Assurance training and indoctrination programs for management, engineering and plant personnel whose activities affect quality (8) Providing technical direction and guidance to the Quality Assurance staff (9) Inspecting, auditing or resiewing practices, records, files, instructions, directions or documents concerned with all areas affecting quality O (10) Scheduling and coordinating audits or sun eillance efTorts in the areas assigned, Q' g documenting findings and reporting results to the Director, Nuclear Safety and management of the audited area 1.3.2.2.3 Supervisors, Quality Control and NDE The Supenisors, Quality Control and NDE report to the Director, Nuclear Safety and are responsible for verifying the implementation of the Quality Control program at ANO. The duties and responsibilities of the Supenisors include the following:

(1) Interface with plant staffin developing quality control requirements and inspection points for operation, maintenance and modification activities related to safety-related (Q-listed) and fire protection-related (F-listed) systems, structures and components (2) Interface with the Supenisor(s), Quality Assurance or their representatives for technical assistance in resohing significant conditions adverse to quality e

' ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-11

(3) Authority to stop unsatisfactory work and authority to place an item in a nonconforming status when such an item is determined to be in violation of purchase docuinents, applicable [

codes and standards or SAR requirements (4) ' Assuring suncillances, inspections, examinations, and reviews cf plant activities and l documents are conducted in accordance with approved procedure; -

(5) Providing technical direction and guidance to their staffs (6) Providing and maintaining a qualified and suitably trained staff to carry out required staff -

functions and formulate programs for maintaining the professional competence of personnel within the Quality Control and NDE sections 1.3.4 Director. Support The Director, Support reports to the Vice President, Operations ANO and is responsible for managing the '

nuclear five-year business plan, including establishing the budget and managing the goals and objectives program for the Nuclear Organization. Management of payroll and accounting is also prosided by the

. Director, Support. He also provides planning, direction, control and overall supenision to the Fitness for f Duty Department and Plant Security Department. Additionally, the control and maintenance of ANO records are a responsibility of the Director, Support. The Nuclear Support Department's organization is shown in Figure 6. The Director, Support is responsible for providing direction and general supenision to the following technical and administrative individuals in support of the Vice President, Operations ANO:

r (1) Manager, Site Business Services ,

(2) Manager, Support (3) Medical Review Officer / Physician (4) Superintendent, Administrative Senices *

(5) Superintendent, Plant Security (6) Coordinators, Special Projects 1.3.4.1 Superintendent, Plant Security ENTERGY REV. 20

~

QA MANUAL OPERATIONS OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-12 1

The Superint:ndent, Plant Security reports to the Director, Support and is responsible for plant security

p. .

including coordination of efTorts of the security force and managing the operation of the security system.

e N ]s 1.3.5 Manager. Materials. Purchasing and Contracts - ANO The Manager, Materials, Purchasing and Contracts - ANO reports to the offsite Director, Materials, Purchasing and Contracts and has direct responsiblity for procurement, receipt, storage and issue of materials, parts and components to be used in Plant maintenance and modification actisities. The Materials Organization is shown in Figure 1. The Manager, Materials, Purchasing and Contracts establishes work priorities for Procurement Engineering. The Manager, Materials, Purchasing and Contracts prosides technical direction and administrative guidance to the following:

1) Superintendent, Stores Operations

2) Superintendent, Inventory Control

3) Supenisor, Procurement

4) Supenisor, Materials Technical i 1.3.6 Manager. Modifications f%

The Manager, Modifications reports to the Vice President, Operations ANO and provides direction, control I.x-J) and overall supenision to the Modifications Depanment in directing and overseeing the implementation of plant modifications and the performance of re'aad support activities at ANO. Responsibilities include:

directing the activities of the ANO Maintenance and Modifications Contractor and other contractors i perfonning modification work at ANO; monitoring the efTectiveness of the ANO Plant Modi 6 cations l Program, and coordinating the resolution of related problems and the implementation of needed program j improvements; and providing engineering services to support the review, preplanning, installation, testing, inspection, and closcout of Modification Packages. The Manager, Modifications is also responsible for the overall direction and conduct of the Post-Modification test program. The Manager, Modifications provides technical direction and administrative guidance to the:

(1) Supenisors, Modifications (2) Supenisor, Project Senices/ Estimating (3) Supenisor, Modifications Central Suppon l ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-13 _

1 1J.7 Director. Training and Emergency Planning ry). The Director, Training and Emergency Planning reports to the Vice President, Operations ANO and is responsible for the training and retraining of plant personnel and general office personnel as established by approved procedures. The Director, Training and Emergency Planning is also responsible for the implementation and maintenance of the ANO Emergency Plan. The Director, Training and Emergency Planning directs the activities of the ANO training staff and provides technical direction and administrative guidance to the:

(1) Supenisor, Operations Training I (2) Supenisor, Simulator Training (3) Supervisor, Simulator Support (4) Manager Emergency Planning '

(5) Supenisor, Maintenance Training (6) Supenisor, Technical Training j (7) Coordinator,INPO Accreditation l

(8) Technical Assistant to Director, Training & Emergency Plamdng l 1.3.8 Director. Design Engineering C

i The Director, Design Engineering reports offsite to the Vice President, Engineering. The responsibilities l of this position include the development and maintenance of engineering programs, policies and procedures; providing engineering senices in support of design, evaluation, analysis, installation, testing, inspection, and operation of Arkansas Nuclear One; effective design modifications to correct deficiencies in plant systems and equipment, improve plant availability, efliciency, safety or productivity and assure thorough and complete design documentation to support effective configuration management for Arkansas Nuclear One.

The Director, Design Engineering provides technical direction and administrative guidance to others who

. direct activities in the areas of plant modifications, operability assessments, maintenance of the design bases of Arkansas Nuclear One, nuclear safety analyses, emironmental qualifications, technical assistance in the resolution of Operations and Maintenance concerns, engineering standards, technical manuals, fire protection, engineering databases, onsite engineering programs, insenice inspection, insenice testing, and on-site welding.

D)

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_ ._ .. __ . . _ _ . _ . _ . . . . . . . - . .. _ . _ _ _ _ _ _ . . _ . _ _ _ - _ _ . ~ . _ . .

, -1.3.9 Independent Review Organizations 0 In addition to the responsibilities of key individuals within the Nuclear Organization who are involved with the overall quality program, the following committees have been established as management tools to independently review activities occurring during the operational phase of ANO.

1.3.9.1 Safety Review Conunittee (SRC) 1.3.9.1.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear power plant operations

b. Nuclear engineering 4

c. Chemistry and radiochemistry

d. Metallurgy

e. Instrumentation and control

[~} f. Radiological safety

g. Mechanical and electrical engineering

h. Quality assurance practices 1.3.9.1.2 Composition 1.3.9.1.2.1 The SRC shall be composed of a chairman and eight to twelve members whose collective qualifications satisfy the requirements of paragraph 2.6.6 of this manual.

1.3.9.1.2.2 The Vice President, Operations ANO shall designate, in writing, the Chairman and all SRC members.

n U ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-15

1.3.9.1.2.3 g

i,] The Chainnan shall designate, in writing, the alternate Chairman in the absence of the SRC Chairman.

1.3.9.1.2.4 All alternate members shall be appointed in writing by the SRC Chainnan to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.

1.3.9.1 J4..~

Consultants shall be utilized as determined by the SRC Chairman to provide expert adsice to the SRC.

1.3.9.1.3 Review Function 1.3.9.1.3.1 The SRC shall meet at least once per calendar quarter during the initial year of unit operation following

t. fuel loading and at least once per six months thereafter. The minimum quorum of the SRC necessary for the perfonnance of the SRC review and audit functions of these technical specifications shall consist of the Chainnan or his designated altentate and at least a majority of the SRC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.

1.3.9.1.3.2 The SRC shall repon to and advise the Vice President, Operations ANO on those areas of responsibility specified in paragraph 1.3.9.1.3.3 below.

1.3.9.1.3.3 The SRC shall review:

a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safet; question.

1 ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-16 4

i 1

l

b. Proposed changes to procedures, equipment or systems which involve an unreviewed Q safety question as defined in 10 CFR 50.59.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in  ;

10 CFR 50.59. l l

d. Proposed changes to Technical Specifications or Operating Licenses.

l l

e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications,  ;

license requirements, or ofinternal procedures or instructions having nuclear safety I significance.  !

f. Significant operating abnormalities or deviations from normal and expected performance I of unit equipment that affect nuclear safety.

1

g. All REPORTABLE EVENTS pursuant to Technical Specification 6.6.2 and 6.6.1 (for Unit I and Unit 2 respectively). )

I h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

i. Reports and meetings minutes of the Plant Safety Committee.  !

j. Proposed changes to the ODCM and PCP.

k. Audits of facility activities as specified in paragraph 18.3.2 of this manual.

1.3.9.1.4 Records of SRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each S'RC meeting shall be prepared, approved and forwarded to the Vice President, Operations ANO within 14 days following each meeting.

ENTERGY QA MANUAL OPERATIONS REV, 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-17

b. Reports of reviews encompassed by paragraph 1.3.9.1.3.3 above shall be prepared.

. , , approved and forwarded to the Vice President, Operations ANO within 14 days following

> \

V completion of the review.

c. Audit reports encompassed by paragraph 18.3.2 of this manual shall be fonvarded to the Vice President, Operations ANO and to the management positions responsible for the areas audited within 30 days after completion of the audit.

1.3.9.2 Plant Safety Cormnittee (PSC) 1.3.9.2.1 The Plant Safety Committee for each operating unit shall function to advise the General Manager, Plant Operations and applicable Plant Manager on all matters related to nuclear safety.

1.3.9.2.2 Composition 1.3.9.2.2.1 m

The Plant Safety Committee for each operating unit shall be composed of eight members of ANO onsite management organization whose selection is described in internal procedures and whose qualifications satisfy the requirements of paragraph 2.6.6 of this manual.

1.3.9.2.2.2 The General Manager, Plant Operations shall designate in writing a PSC Chairman and at least one Alternate Chairman.

1.3.9.2.2.3 All alternate members shall be appointed in writing by the PSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSC activities at any one time.

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1.3.9.2.2.4 rh

() For Unit 2 PSC, if Core Protection Calculator (CPC) Software is being reviewed, a nuclear software expert shall be present as a voting member. If one of the members of the Plant Safety Conunittee meets the qualification requirements for this position, the requirement to have this member is satisfied. This membership may be filled by two appropriately qualified individuals who shall ballot with a single combined vote. Cencric qualifications for this membership shall be as follows-

/

One Individual The Nuclear Software Expert shall have as a minimum a Bachelor's degree in Science or Engineering, (Nuclear preferred) in accordance with ANSI N18.1. In addition, he shall have a minimum of four years of I technical experience, of which a minimum of two years shall be in Nuclear Engineering and a minimum of two years shall be in Software Engineering. (Software Engineering is that branch o' e: .cc and technology which deals with the design and use of software. Software Engineering is a discipline directed to the production and modification of computer programs that are correct, efficient, flexible, maintainable, and understandable, in reasonable time spans, and at reasonable costs.) The two years of technical j experience in Software Engineering may be general software experience not necessarily related to the j software of the Core Protection Calculator System. One of these two years of experience shall be with

)

Q certified computer programs.

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Two Individuals One of the individuals shall meet the requirements of the Nuclear Engineering portion of the above. The second individual shall have a Bachelor of Science degree (digital computer specialty) and meet the Software Engineering requirements of the above.

The membership (the Nuclear Software Expert or the Digital Computer Specialist) shall be knowledgeable of the Core Protection Calculator System with regard to:

a. The software modules, their interactions with each other and with the data base.

b. The relationship between operator's module inputs and the trip variables.

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c. The relationship between sensor input signals and the trip variable. l p '

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-19 I

d. The design basis of the Core Protection Calculator System.

c. The approved software change procedure and documentation requirements of a software change.

f. The security of the computer memory and access procedures to the memory.

I 1.3.9.2.3. Review Function 1.3.9.2.3.1 l

The PSC for each operating unit shall meet at least once per calendar month and as convened by the PSC

)

Chairman or his designated alternate. The minimum quorum of the PSC necessary for the performance of the PSC responsibilities designated in this manual shall consist of the Chairman or his designated alternate and four members including alternates. The PSC Chairman shall ensure that adequate expenise is present during meetings to evaluate material before the PSC.

l 1.3.9.2.3.2 r%

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l The Plant Safety Committee shall be responsible for. i

a. Resiew of 1) all station administrative procedures reconunended in Appendix A of Reg.

l Guide 1.33 (November,1972 for Unit I and Revision 2, February,1978 for Unit 2) and changes in intent thereto, 2) changes to the Emergency Operating Procedures for each j operating unit required to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in Section 7.1 of Generic Letter 82-33,3) changes to Core Protection Calculator (CPC) Software (for Unit 2), and 4) any other proposed procedures or changes thereto as determinedc' y the General Manager, Plant Operatiorn or applicable Plant Manager,

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Resiew of all proposed changes to Appendix "A" Technical Specifications for each operating unit. ,

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s:

d. Resiew of all proposed changes or modifications to unit systems or equipment that atiect nuclear safety.

t K.

e. Investigation of all siolations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendation to prevent recurrence to the applicable Plant Manager, General Manager, Plant Operations and the Chairman of the Safety Review Committee.

f. Review of all REPORTABLE EVENTS.

g. Review of facility operations to detect potential nuclear safety hazards.

h. Performance of special reviews, investigations or analyses, and reports thereon as requested by a Plant Manager, General Manager, Plant Operations or the Safety Resiew Committee.

i. Review of the Plant Security Plan and submittal of recommended changes to the General Manager, Plant Operations and Safety Review Committee.

' j. Review of th: Emergency Plan and submittal of recommended changes to the General k Manager, Plant Operations and Safety Review Committee.

k. Review of changes 16 the Offsite Dose Calculation Manual and Process Control Program.

1. Review of changes to the Fire Protection Program and submittal of reconunended changes to the General Manager, Plant Operations and Safety Review Committee.

m. Review of proposed procedures and changes to procedures which involve an unreviewed safety question as defined in 10CFR50.59.

l

. n. Review and documentation ofjudgment concerning extended operation (longer than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) with a PPS trip channel in bypass. Review shall determine whether to leave the trip l channel in bypass, place the channel in trip, and/or repair the defective channel.

QD ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR'ONE SECTION: 1.0 ORGANIZATION PAGE l-21 l l

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1.3.9.2.3.3 The Plant Safety Committee shall:

l-a: Reconunend in writing their approval or disapproval of items considered under paragraph 1.3.8.2.3.2(a) through (d) above.

1

b. Render determinations in writing with regard to whether or not each item considered under paragraph 1.3.8.2.3.2(a) through (e) above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President, Operations ANO and the Safety Review Committee of disagreement between the PSC and a Plant Manager or the General Manager, Plant Operations; how1ever, the General Manager, Plant Operations shall have responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1 for each operating unit.

1.3.9.2.4 The Plant Safety Committee shall maintain written minutes of each PSC meeting that, at a minimum, document the results of all PSC activities performed under paragraphs 1.3.8.2.3.2 and 1.3.8.2.3.3 above.

Copies shall be provided to the applicable Plant Manager, General Manager, Plant Operations and Chairman of the Safety Review Committee.

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1.4 ENTERGY OPERATIONS OFFSITE ORG ANIZATION 1.4.1 President & Chief Executive Officer The President & Chief Executive Officer has the ultimate responsibility for the safe and reliable operation of the Entergy Operations' nuclear sites. He provides guidance with regard to quality assurance and internal audit policy, coordinates foreign visits, interfaces with World Association of Nuclear Operations, interfaces with the state public senice commissions, and oversees strategic planning.

He delegates authority and responsibility for the operation and support of ANO through the Executive Vice 1

President & Chief Operating Officer; the Director, Business Senices; the Director, Nuclear Fuels; and the Director, Total Quality.

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ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-22

_ _ . . . _ . . . . _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ . . _ . . ___m.__._._ ._ ,

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l 1,4.2 ' Executive Vice President & Chief Operating Omcer

. The Executive Vice President & Chief Operating Officer has the responsibility to oversee all operations and engineering functions of Entergy Operations. He delegates authority and responsibility for the operation and support of ANO through the Vice President, Operations ANO; the Vice President,-

) Engineering; and the Vice President, Operations Support. It is the responsibility of the Executive Vice l President & Chief Operating Officer to assure that all safety-related activities under his direction are performed following the guidelines of the Headquarters Quality Assurance Manual and the ANO QAMO.

The organization is shown on Figure 1.

1.4.2.1 Vice President, Operations Support

[ The Vice President, Operations Support reports directly to the executive Vice President and Chief

Operating Officer and is responsible for administering corporate support functions in the areas of  !

radiological protection, radioactive waste management, chemistry, emironmental senices, operations,  ;

maintenance, outage management, security, emergency planning, tecimology transfer, licensing; plant assessments, information technology, material requirements and materials, purchasing and contracts. It is the responsibility of the Vice President, Operations, Support to assure that these functions performed for 4 ANO are performed in accordance with the requirements of the ANO Quality Assurance program.

1.4.2.1.1 Director, Materials Purchasing & Contracts The Director, Materials, Purchasing and Contracts reports to the Vice President Operations Support and is responsible for the oversight and development of purchasing policies and procedures consistent across Entergy Operations nuclear sites and Headquarters and providing the direction and administration l

necessary relative to quality responsibilities as they relate to the ANO Quality Assurance Program.  ;

b 1.4.2.1.1.1. Manager, Material Requirements The Manager, Material Requirements reports to the Director, Materials, Purchasing and Contracts and is  !

responsible for:

1. Evaluating quality assurance programs and activities of ANO suppliers and contractors of quality-S related items, spare parts, and senices through reviews, surveillances, and audits;

2. Conducting pre-award evaluations for quality requirements of vendors, suppliers, and contractors, 4

where applicable.

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3. Maintaining a Qualified Suppliers List (QSL) for use in procuring safety-related items, spare parts, i

f~}

\. s and senices; and

4. Performing design review and fuel fabrication audits as necessary to ensure that nuclear fuel procured for use by Entergy Operations is designed and fabricated in accordance with applicable codes, standards, and regulations.

The authority for the accomplishment of the above activities is delegated to the incumbent's staff.

1.4.2.2 Director, Nuclear Fuels The Director, Nuclear Fuels reports to the Executive Vice President and Chief Operating Officer and is responsible for the procurement of nuclear fuel for ANO, the provision of nuclear fuel cash flow and cost projections for use in company business plan and fuel financing activities, the maintenance of the Official Entergy Operations Nuclear Operating Schedule, and the oversight of nuclear fuel accounting actisities.

1.4.2.3 Vice President, Engineering The Vice President, Engineering reports to the Executive Vice President and Chief Operating Oflicer and O) v .

is responsible for providing nuclear engineering senices for ANO, as requested. The incumbent is responsible for Design Engineering, fuel design and core design. In addition, the incumbent has overall administrative, programmatic and operational control of the Entergy Operations, Inc. Welding Program.

1.4.3 Vice President. Human Resources & Administration The Vice President Human Resources & Administration is responsible for the administration of functions associated with Corporate Services and Human Resources. He delegates authority and responsibility for the accomplishment of the above activities through the Director, Human Resources. It is the responsibility of the Vice President, Human Resources & Administration to assure that the safety-related activities under his direction are performed following the guidelines of the Headquarters Quality Assurance Program and the ANO QAMO.

O ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 1.0 ORGANIZATION PAGE l-24

4 1.4.3.1 Director, Human Resources l s

[ The Director, Human Resources reports to the Vice President, Human Resources and Administration and is I responsible for functions associated with programs dealing with employees compensation, benefits, employee and labor relations, aflirmative action, recruitment, industrial safety, succession planning and human resource development. He delegates authority and responsibility for employee relations activities at ANO through the Manager, Human Resources-ANO.

1.5 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES i

Entergy Arkansas, Inc. and Entergy Operations, Inc. are joint licensees under the facility operating license condition, each responsible for specific areas andjointly responsible for regulatory compliance and response. Entergy Arkansas, Inc. is licensed to possess the facility and Entergy Operations, Inc. is licensed 1

to possess, use and operate the facility.

4 Each supplier of equipment, material or senices and each maintenance or modification contractor is responsible for administering the applicable quality assurance / quality control functions as required by a

ANO. The Quality Organization is responsible for assuring by surveillance, inspection, audit or resiew of objective evidence that onsite functions are accomplished for systems, structures and senices that affect the I safety and integrity of the plant.

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2.0 OUALITY ASSURANCE PROGRAM

-.O Jj\ 2.1 SCOPE This QA Program is to assure that ANO is operated in a safe, reliable and efEcient manner and in

?- accordance with NRC regulations, applicable industrial standards and codes and applicable Company policies, rules, procedures and licensing documents. A matrix of quality procedures cross-referenced to each criterion of 10CFR50, Appendix B, is included in Table 2 to tids manual.

2.2 GENERAL 2.2.1 This QA Program is applied to those safety-related structures, systems and components and to those expendable and/or consumable items

• whose satisfactory performance is required to prevent accidents which may cause undue risk to the health ar.d safety of the public or to mitigate the consequences of such accidents if they were to occur. These structures, systems and components are identified in the summary level and component level Q-lists for each nuclear unit. The Summary Level Q-Lists (SLQL) are located

-. in the SARs and information for the Component Level Q-lists (CLQL) is maintained current in the Station Information Management System (SIMS) for each nuclear unit. When structures, systems and components as a whole are on the SLQL or CLQL, portions not associated with a loss of safety function as determined by Engineering are to be considered Non-Q, unless othenvise dispositioned by Engineering.

• Expendable and/or consumable items are to include, as a nunimum: weld rods, boric acid, and diesel fuel.

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2.2.2 m

Expendable and/or consumable items where quality is necessary for the performance of Q-listed structures, systems and components are identified and controlled in accordance with Technical Specifications and/or procedures.

The following expendable and/or consumable items are to be controlled in the Ollowing manner to assure senice quality:

(1) Diesel Fuel - Senice quality is ensured by applicable provisions / tests required by the Technical Specification for each operating nuclear unit.

(2) Welding Rod - Senice quality is ensured by procurement from an evaluated source, requiring material test results when specified by the ASME Code or applicable design document, and controlling the rod on-site prior to use to prevent degradation.

(3) Boric Acid - Senice quality is ensured by procurement from an evaluated source, requiring a batch analysis to ensure conformance with our specification requirements or by commercial grade procurement and dedication in accordance with approved procedures, and on-site control f3 t prior to use to prevent degradation.

2.2.3 The quality program for transport packages containing radioactive materials is addressed in Appendix A of this manual and implemented through appropriate approved procedures. The effectiveness of tids quality program is verified through scheduled audits conducted by the Quality Organization under the cognizance of i

the SRC.

1 ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 2.0 QA PROGRAM PAGE 2-2

2.2.4 t'h '

! The quality program for fire protection is addressed in Appendix B of this manual and in the applicable section of the SAR for each operating nuclear unit and implemented through appropriate approved procedures.

The effectiveness of the fire protection program is verified through scheduled audits conducted by the Quality Organization under the cognizance of the SRC.

2.2.5 The quality program for the station blackout non-safety system and equipment used to meet the requirements of 10CFR50.63 is addressed in Appendix C of this manual and is implemented through appropriate approved procedures. The effectiveness of this program is verified through scheduled audits conducted by the Quality Organization under the cognizance of the SRC.

2.2.6 The System Level Q-List (SLQL) (as part of the SAR) is under the control of the Directe Nuclear Safety.

The Licensing Department ensures that reviews, approvals, and changes thereto are performed in accordance with approved procedures. Changes to the SLQL require review / approval by the applicable Manager, q

(d .

Engineering; and Director, Nuclear Safety. ANO Document Control shall make distributions to the SAR in accordance with approved procedures.

2.2.7 The Component Level Q-List (CLQL) is maintained on a computer data base (SIMS) and is controlled in accordance with approved procedures. Engineering is responsible for the technical adequacy of the CLQL and the administrative controls of the CLQL within SIMS. Evaluations, reviews and approvals to changes to the CLQL are performed in accordance with applicable procedures.

2.2.8 The Component Level F-list (CLFL) is maintained on the SIMS component data base by Engineering.

Components classified as "F" on this list fall under the requirements of Appendix B of this manual. The controls for this list are similar to the controls utilized for the Q-list.

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2.2.9 i

Components that are not Q-listed or F-listed and which are subject to ASME code requirements or similar

. design standards, regulatory requirements or licensing commitments or other ANO conunitments are classified as "S" in the SIMS component data base. The controls for this list are similar to controls for the Q-list. This list is also referred to as the Component Level S-list (CLSL).

2.3 RESPONSIBILITIES 2.3.1 ANO recognizes that quality assurance is an interdisciplinary ftmetion involving many organizational groups, encompasses many functions and activities and extends to various levels in all participating organizations (from the Entergy Operations President and Chief Executive Officer to all workers whose actisities may influence quality). The QA Program designates responsibilities and duties of specific indisiduals, which may be performed by their appointed designees.

i 2.3.2 The QA Program assigns the responsibility for quality to the departments performing the work and includes as a basic requirement that individuals responsible for verification of conformance are qualified and do not perform or directly supenise the work.

Additionally, independent reviews, audits and surveillances are provided by individuals not reporting to the groups responsible for performing the work.

2.3.3 The QA Program also includes provisions that require suppliers, contractors, subcontractors, consultants. etc.

to maintain and use quality assurance programs reviewed and approved by the Manager, Material Requirements. Audits or surveillances by Material Requirements provide assurance of compliance with applicable procedures.

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2.3.4 e.,

[ )

v On site quality control of nuclear fuel is the responsibility of System Engineering and is implemented through the use of plant administrative procedures. These procedures include the receipt, inspection handling, storage -

and accountability of Special Nuclear Material (SNM). Indisiduals who perform receipt inspections are qualified in accordance with paragraph 2.6.3 of this manual. The Director, Nuclear Safety or designec maintains a listing of those individuals qualified to perform receipt inspection on nuclear fuel.

2.4 PROCEDURES 1

2.4.1 Activities which affect quality are defined in appropriate procedures, which are developed to cover  ;

administration and control. The procedures state the policies and instructions necessaiy to fulfill the intent of the QA Program. Procedures provide for standard forms, lists, and checkoffs used in documenting the inspections, certifications, resiews, surveillances and audits. Programs and procedures are modified or supplemented from time-to-time as the need for change arises during the life of the plant. Quality program policies, procedures and instructions are contained in the documents listed in Table 3.

[m l

O' 2.4.2 -

Procedures assure that activities affecting quality ate performed under suitably controlled conditions.

Controlled conditions include the use of appropriate equipment, suitable environmental conditions for performing the activity such as adequate cleanness and assurance that required prerequisites for the given activity have been satisfied. Administrative procedures also assure that the need for special controls, processes, tests and equipment to attain the required quality and the need for verification of quality by inspections, evaluations or tests is taken into account.

2.5 PROGRAM REVISION AND CONTROL 2.5.1 Program revision and control shall be the responsibility of the Director, Nuclear Safety.

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,I 2.5.2 i

Proposed changes to this manual are to be submitted by the Manager, Nuclear Safety to affected management J

personnel for review and comment prior to approval and transmittal to the Nuclear Regulatory Commission.

' After resolution of comments, changes are to be approved by a Supervisor, Quality Assurance; Director,

Nuclear Safety; and the Vice President, Operations ANO.

l 2.5.3 Changes to the program which do not reduce commitments, are to be submitted to the Nuclear Regulatory i Conunission with the ANO-1 Safety Analysis Report submittal. Changes to the program description that reduce the commitments are to be submitted and approved by the Nuclear Regulatory Commission prior to implementation. The Director, Nuclear Safety, or his designee, is to determine if changes do or do not reduce the commitments of the QA Program.

2.6 PERSONNEL f

2.6.1 Employees whose duties and responsibilities are related to the QA Program activities at or in support of ANO V} are to participate in appropriate indoctrination an'd tmining programs to assure that suitable proficiency is achieved and maintained in the work they are performing. Such training shall include, as a minimum: plant security (badged personnel only), discussion of the overall company policies, procedures and instructions which establish the QA Program, an explanation of the quality organization and a discussion of those procedures which implement the QA Program related to the employee's specificjob-related activity.

2.6.2 The educatiren, experience and responsibility requirements ofindividuals involved in the QA Program are documentej in job descriptions which are approved and periodically reviewed by management. Requirements for education, experience and proficiency levels are commensurate with the degree ofimportance of the job assignment. Experience and training requirements for plant stafrpersonnel are to meet the requirements of ANSI N18.1-1971 and Regulatory Guide 1.8 (9n5), unless otherwise noted in Table 1. Personnel whose p ENTERGY QA MANUAL OPERATIONS REV. 20 Q OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 2.0 QA PROGRAM PAGE 2-6

4 l

1 qualifications do not meet those specified in ANSI N18.1 1971, end who are performing inspection,

, examination and testing activities during the operational phase of the plant, are to meet the requirements of  ;

k ANSI N45.2.6 1978 unless otherwise noted in Table 1.

l 2.6.3 1

l

Personnel performing inspection and examination activities are to be indoctrinated and trained to assure they I

are aware of the requirements which govern their activity, inspection and examination personnel are to be i-qualified according to the applicable codes, standards, specifications, regulatory requirements and approved

. procedures. Personnel prforming inspections on those activities occurring during the operational phase that are comparable in nature and extent to related activities occurring during initial plant design and construction i are to meet the provisions of Regulatory Guide 1.58, Rev.1 (9/80) and ANSI N45.2.6 1978 in lieu of ANSI i N18.1-1971.

a 2.6.4

!' Personnel involved with welding of materials, systems or components are to meet the appropriate qualification requirements of the ASME Boiler and Pressure Vessel Code, Sections III and XI, or for structural welds, the

! American Welding Society (AWS) Structural Steel Code DI.I. Personnel involved with nondestmetive examination of materials, components or systems are to meet the qualification requirements of the American

Society Nondestructive Testing Recommended Practice SNT-TC-1 A or ASME Section 111 and XI for ASME 1 Code materials, components or systems. Personnel are to be certified to perform these tasks in accordance j with these codes and standards.

4 e

1 2.6.5 i

i Personnel performing audits of the QA Program are to meet the experience, training and qualification / certification requirements of ANSI N45.2.23-1978 and Regulatory Guide 1.146 (S/80) unless otherwise noted in Table 1.

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2.6.6

,N I Personnel appointed to the SRC shall collectively have the experience and competence required by ANSI /ANS 3,1-1981 to review problems in the areas specified in paragraph 1.3.9.1.1 of this manual. Onsite manageme :t l personnel appointed to the PSC shall have the technical experience and competence required by ANSI /ANS  !

l 3.1-1981 for Managers, Professional-Technical, or Engineering and Technical Support personnel. '

2.6.7 Training records are to be maintained in accordance with approved procedures. For formal training programs, j documentation is to include the objective, content of the program, attendees and date of attendance.

l 2.7 PROGRAM REVIEW 2.7.1 The Director, Nuclear Safety through the Supervisor (s), Quality Assurance is responsible for a resiew of the QA Program on an annual basis to determine the effectiveness and proper implementation of the QA Program.

l (j 2.7.2 Management reviews of the status and adequacy of the QA Program are accomplished through regular reports and presentations by the Quality Organization and through reviews of quality assurance reports. Quality Assmance reports supply data on the status of outstanding audit and corrective action items and may identify the status of other significant QA Program activities as requested by management.

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~3.0 DESIGN CONTROL

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() 3.1 SCOPE Design activities are to be controlled to assure that proposed plant changes to the structures, systems, equipment and components conform to applicable regulatory requirements and that design bases are correctly translated into appropriate design documents. Design control activities are to be in accordance with the requirements of Regulatory Guide 1.64, Rev. 2 (6/76), unless otherwise noted in Table 1, 3.2 GENERAL I

3.2.1 Engineering is responsible for the continued upgrading and modification of plant design. Design documents i 1

(drawings, specifications, procedures and instructions) originating or released through these departments are to I

be based upon the regulatory requirements, licensing-based documents, functional requirements, quality standards and design bases in accordance with NRC licensing requirements. Design activities may include calculations, analyses, materials selection, equipment arrangement and layouts, accessibility for inservice

inspection, and the specification of test and inspection criteria. Those design activities performed by individuals within Engineering are controlled by the use of applicable administrative and depanmental procedures. These  ;

procedures include controls to assure that verified computer codes are certified for use and that their use is specified. l 3.2.2 Design standards and requirements are to be at least equivalent to those employed during the construction of the plant and are to be consistent with the Technical Specifications and License requirements.

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3.3 DESIGN INTERFACE Q Design control activities include measures for the identification and control of design interfaces between the various engineering sections within Engineering, between Engineering and other Nuclear Organizations, and between Engineering and firms / suppliers outside the Nuclear Organization. These measures include the development of procedures among the participating organizations for the resiew, approval, release, distribution l

and revision of documents invohing design interface. Coordination of the interface contrcd is the responsibility i i

of the originating organization's management unless otherwise specified in a procedure applicable to the design activity. Design information between interfacing organizations is to be documented and retained for lifetime i

records.

3.4 DESIGN VERIFICATION 3.4.1 -

To assure the design is adequate and the above requirements and procedures are implemented. Engineering is to verify the adequacy of the design through the performance of design reviews, the use of alternate or simplified calculation methods, or the performance of a qualification testing program. The extent and depth of design g verification performed by the responsible engineering section is determined by an assigned engineering resiewer i based upon the importance and complexity of the design, the degree of standardization and its similarity with proven designs. In all cases, the design verification is to be complete prior to relying upon the component, system or structure to perform its function.

3.4.2 The verification process is to be performed by competent individuals or groups other than those who performed or supenised the design but who may be from the same engineering section. This verification, however, may be performed by the originator's supenisor in accordance with departmental procedures if he is the only indhidual in the organization competent to perform the verification and provided the need is individually documented and approved in advance by the responsible Manager or Superintendent. The frequency and effectiveness of the use of Supenisors as design verifiers is to be verified by Quality personnel through scheduled audits to guard against abuse. Where changes to previously verified designs have been made, design verifications are required for the change, including evaluation of the effects of the changes on the overall design.

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OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 3.0 DESIGN CONTROL PAGE 3 2

i 3.4.3

) When a test program is used to verify the adequacy of a design, it is to include suitable qualification testing of a prototype or initial production unit under the most adverse design conditions and carried out in accordance with documented procedures and/or instructions. Testing is to be perforraed as early as possible prior to installation J

of plant equipment, or prior to the point when the installation would become irreversible.

3.4.4 Design work performed by organizations outside of the Nuclear Organization is to receive a documented review and approval by engineering personnel in accordance with applicable departmental procedures.

3.5 DESIGN CHANGE 3.5.I Methods for the preparation, review, approval and implementation of design changes, including field changes, i

are documented in departmental procedures for Engineering. Design changes are subject to resiew and

,_ verification by the same engineering section which reviewed and verified the original design unicss otherwise specified in departmental procedures for design control. If changes to an approved design are required to meet plant requirements or conditions, Field Change Requests (FCR) may be issued or otherwise documented by a cognizant engineer and transmitted with the changes for review and approval in accordance with applicable departmental procedures.

3.5.2 Changes from specified design inputs, such as design bases, regubtory requirements, codes and standards (including quality standards) are to be identified, approved, documented and controlled through applicable departmental procedures.

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I 3.5.3 l (j During preparation of a design change, the responsible engineering section is to perform a review per 10CFR50.59 to verify compliance with the S AR and to determine if NRC approval of the design change is required. The documented 50.59 review is to be reviewed and approved by the PSC. In addition, any ,

10CFR50.59 evaluations shall also be reviewed and approved by the SRC.

i j 3.5.4 i

The conformance of design changes to regulatory and license commitments, quality codes and standards, and design specifications from initiation through installation / implementation is verified by Quality personnel through audit, surveillance, or inspection activities.

I 3.6 CORRECTIVE ACTIONS i When design changes are made as a result of design deficiencies or errors, corrective actions (for significant conditions) are to be taken in accordance with Section 16.0 to determine the root cause and to institute appropriate changes in the design process and/or QA Program to prevent recurrence. When a significant design change is necessary because of an incorrect design, the design process and verification procedures shall be

.f

'Q reviewed and modified as necessary.

4 3.7 DESIGN RECORDS The Superintendent, Administrative Services is responsible for maintaining lifetime records of the design documents for the construction and testing phases, and for maintaining records of the upgrading or modification

, of these documents as described in this section.

The controls for maintaining these records are established by specific procedures described in Section 17.0 of this manual. These records provide the historic reference necessary for the safe and reliable operation of ANO.

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4.0 PROCUREMENT DOCUMENT CONTROL l r,

) 4.1 SCOPE Requirements for the procurement ofitems and senices are to be clearly stated and documented to assure that applicable regulatory requirements, design bases, technical requirements and quality assurance criteria are included or referenced in the procurement documents. Procu_ement document control activities are to be in accordance with approved procedures and are to meet the provisions set fonh in NRC Regulatory Guide 1.123, l

Rev, I (7/77), unless otherwise noted in Table 1.  ;

4.2 PROCUREMEN'T DOCUMENTS .

4.2.1 l The procurement of materials, parts and components is generated through the preparation of a Purchase Requisition and subsequent issuance of a Purchase Order, or when senices from the Vendor are required, through the preparation of a Contract Request and subsequent issuance of a Contract. The preparation, resiew, approval and issuance of these procurement documents are to be in accordance with applicable purchasing and j i

,m contract administration procedures. Purchase Orders and Contracts are issued through the Procurement V) Section. Senices obtained from other Entergy Operations Incorporated (EOI) sites are initiated through documented agreements in accordance with site procedures.

4.2.2 Procurement documents are to include or reference specific design specifications for the items or senices to be procured which define specific codes, standards, tests, inspections, environmental qualifications, and records to be applied and/or furnished. For standard "off-the-shelf" items, reference to the item's catalog number and identification number may be included on the procurement document in lieu of a design specification. New or revised specifications for replacement items are to be evaluated by the responsible engineering organization against the original specification for the item. The evaluation is to be in accordance with applicable engineering procedures and will result in the establishment of new baseline and technical quality requirements, which are to be used for subsequent procurements.

ENTERGY QA MANUAL OPERATIONS REV. 20

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J 4.2.3

, Procurement documents are also to include the identification of quality assurance program requirements applicable to the items or senices procured. Procurement documents also establish requirements for source audits and inspections, extension of the procurement requirements to lower-tier suppliers or subcontractors, and preparation and delivery of documentation. These requirements may either be in the form of documents attached to the PO or Contract or by incorporating them in the specific design specifications. Quality programs 4

4 are to be specified by invoking the appropriate sections of 10CFR50, Appendix B, the appropriate ANSI standards and/or the appropriate ANO-generated quality requirements for items or senices. The appropriate sections of the ASME Boiler and Pressure Vessel Code are to be invoked for items originally designed to meet ASME requirements.

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4.3 REVIEW OF PROCUREhENT DOCUMENTS 4.3.1 The appropriate sections within the ANO organization, as identified in the applicable procedures for procurement and contract administration activities, are to review safety-related procurement )1

) documents to assure that the required quality requirements (including source surveillance and/or inspection) are imposed on suppliers / contractors. I i

i

() 4.3.2 The incorporation of appropriate quality requirements in procurement documents is verified by )

i Quality through periodic review in audits, surveillances or inspection activities.

l 4.4 CHANGES TO PROCUREMENT DOCUMENTS

. Changes to procurement documents are to have the same degree of control and review as imposed on the 4 original documents. Changes such as inconsequential editorial corrections or changes to commercial terms and l conditions may be made by Procurement or Contract Administration personnel, as appropriate, after l I

l concurrence from the originator or organization which originated the document. I i

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DOCUMENT CONTROL l

i 5.0 INSTRUCTION

S. PROCEDURE

S AND DRAWINGS m

5.1 SCOPE 5.1.1 Instructions, procedures and drawings are provided for the control of those activities which affect quality aad safety at ANO. Activities covered by written procedures include, as a minimum: administrative, general plant operations, start-up, shutdown, power operation and load changing, process monitoring, fuel handling, modification, maintenance and repair, radiation control, calibration and test, chemical-radiochemical control, plant emergencies, test and inspection, quality assurance, quality control, and off-site activities in support of

ANO. The format, content and philosophy ofinstructions and procedures are to comply with the guidelines in ANSI N18.7-1976 and Regulatory Guide 1.33, Rev. 2 (2/78) unless otherwise noted in Table 1. l l

l 5.1.2 i instructions and procedures are also prmided for the control %ctivities relating to the repair, replacement or ,

l modifications to ASME Code, Section ill, Class 1,2 or 3 compunents required to be operable to mitigate the consequences of a postulated accident.

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5.2 GENERAL i

5.2.1 J

Instructions, procedures and drawings are to include appropriate quantitative criteria such as dimensions, tolerances and operating limits and/or qualitative criteria such as comparative workmanship samples to determine that important activities have been satisfactorily accomplished. Each procedure is to be sufficiently detailed so that a qualified individual may perform the required function (s) without direct supervision and is to include measures to document the activity being performed.

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5.2.2

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Q To assure the accomplistunent of activities in accordance with approved instructions, procedures and drawings, each supenisor is responsible for quality compliance of his personnel. Verification that activities are accomplished in accordance with approved instructions, procedures and drawings is obtained through various levels of surveillance, inspection and audit by the Quality Organization.

5.3 REVIEW OF INSTRUCTIONS, PROCEDURES AND DRAWINGS 5.3.1

, instmetions, procedures and drawings are prepared, reviewed and approved in accordance with applicable administrative procedures.

j 5.3.2 Procedures required by Technical Specifications 6.8.1 (for Unit I and Unit 2) which affect nuclear safety, as determined by the General Manager, Plant Operations, and changes thereto, shall be reviewed as follows:

f3

-Q a. Each procedure or change shall be independently reviewed by a qualified individual 4

knowledgeable in the area affected other than the individual who prepared the procedure or procedure change. This review shall include a determination of whether or not additional cross-disciplinary reviews are necessary. If deemed necessary, the resiews shall be performed by the review personnel of the appropriate discipline (s).

I

b. Individuals performing these reviews shall meet the applicable qualifications of ANSI /ANS 3.1-1981, Section 4.0, excluding subsections 4.3.2 and 4.5, and by approved to perform these reviews in a given nrea by the General Manager, Plant Operations.

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c. Those procedures and programs specified by QAMO Section 1.3.9.2.3.2 and changes in intent thereto, shall be resiewed by the PSC and approved by the responsible Major Department Head

, (Q or the applicable Plant Manager prior to implementation. ,

d. Those procedures and programs specified by Technical Specification 6.8.1, and changes in intent thereto, with the exception of those specified in QAMO Section 1.3.9.2.3.2 shall be approsed by the appropriate Department Head or designee as specified in station administrative procedures.

c. Resiew of the procedure or procedure change will include a determination of whether or not an unreviewed safety question is involveu. This determination will be based on the review of a written safety tvaluation prepared by a qualified individual, or documentation that a safety evaluation is not required. PSC review, SRC review, and NRC approval ofitems involving unreviewed safety questions shall be obtained prior to station approval for implementation.

f. Overall Administrative Procedures (OP-1000.XXX and OP-6000.XXX Series) and Engineering Administrative Procedures (OP 5000.XXX Series) are also reviewed by the Quality Organization to verify compliance to the QA program.

g. Written records of reviews shall be prepared and maintained in accordance with Technical Specifications 6.9 and 6.10 (for Unit 1 and Unit 2 respectively) and Section 17.0 of this manual.

5.3.3 Procedures and instructions are to be reviewed upon identification of new or revised source material potentially affecting the content of procedures, or prior to use if the procedure / instruction is not used routinely to determine if changes are necessary or desirable. Audits by the Quality Assurance Department are performed on at least a biennial basis to verify the effectiveness of controls used to maintain procedures current. Applicable procedures (i.e., those that relate to the incident cause) are to be reviewed following an unusual incident such as an accident, unexpected transient, significant operator error or egmpment j i

malfunction. Applicable procedures are also to be reviewed following any modification to a plant system. j 1

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PROCEDURES AND DRAWINGS {

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5.3.4 n

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\s t Drawings related to plant changes and modifications are controlled as described in Section 3.0 and 6.0 of this manual.

5.4 CHANGES TO PROCEDURES 5.4.1 Changes or revisions to approved instructions, procedures and drawings are to be reviewed and approved by the same organizations or groups that performed the original review, unless otherwise noted in specific ANO procedures, and controlled in the same manner as the original.

5.4.2 I l

l Temporary changes to approved procedures may be made in accordance with either the applicable Technical Specifications or approved procedures for those procedures which are not Technical Specifications related. In the event of an emergency not covered by an approved procedure, Operations personnel may take action, without obtaining approvals, to minimize personnel injury and damage to the facility and to protect health and

(,1 - safety.

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OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 5.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS PAGE 5-4

6.0 DOCUMENT CObfrROL Q 6.1 SCOPE The various quality program documents identified in Table 3 provide means to control the review, approval, issuance, use and retrievability of documents, such as calculations, computer codes, analyses, QA Manual Operations, SAR, instructions, procedures, specifications, manuals and drawings, including changes thereto, which prescribe activities affecting quality.

6.2 RESPONSIBILITIES 6.2.1 i Each organization originating documents which prescribe activities affecting quality is responsible for the establishment of document control procedures which identify individuals or groups responsible for preparation, review, approval and maintenance of the document and for the issuance of these procedures to

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l the affected individuals or groups.

6.2.2

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Review of these documents for concurrence with quality-related requirements is to be performed by the Quality Organization and/or by the appropriate reviewer as described in approved procedures.

l 6.2.3 j

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The Superintendent. Administrative Senices is responsible for the control and issuance of procedures and l l

revisions thereto to assure distribution in accordance with approved procedures. The Superintendent,

- Administrative Senices is also responsible for the storage and control of approved historical plant docurdents and the storage of historical drawing records. The Superintendent, Administrative Senices is responsible for the control and issuance of drawings and revisions thereto to ensure that they reflect the as-built conditions of the plant.

l ENTERGY REV. 20 t

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6.3 IDENTIFICATION

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( Documents are to be identified by a title descriptive of their purpose or applicability and marked or stamped

%./ )

as to their current status (Draft, For Information Only, Void, etc.) per departmental procedures. Resision status of a document is to be identified in document registers. distribution lists and/or within the revision record page/ block of the document.

6.4 DISTRIBlTTION Distribution lists and/or document registers are to be maintained by the organization responsible for issuance of the document. These lists are to identify the revisio 1 status of the document and are to be reviewed and updated periodically by the responsible organization to maintain them in a current status.

These lists are available to individuals using the document to assure they are in receipt of the current document. These measures are to preclude the possibility of using outdated or inappropriate documents.

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6.5 CHANGES 6.5.1 Changes to controlled documents are to be reviewed and approved by the same organizations which bg performed the original review and approval unless othenvise specified in departmental procedures applicable to the affected actisity.

6.5.2 l

Obsolete or superceded decuments are to be destroyed or marked to prevent inadvertent use in accordance 4

with applicable document control procedures.

6.6 STORAGE l

Documents which affect quality are to be stored and maintained per approved site procedures and controlled as described in Section 17.0 of this manual.

6.7 VERIFICATION Quality personnel through their various levels of quality raiew, surveillance, audit, and inspection activities assure proper documents are being used and made availabic to those individuals performing the work.

(( ENTERGY OPERATIONS QA MANUAL OPERATIONS REV. 20 j ARKANSAS NUCLEAR ONE SECTION: 6.0 DOCUMENT CONTROL PAGE 6-2

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7.0 CONTROL OF PURCHASED MATERIAL. EOUIPMENT AND SERVICES i l

O V 7.1 SCOPE l l

The purchase of material, equipment and senices is controlled to assure that, whether purchased directly or I

through vendors, the material, equipment and senices which affect quality conform to the procurement documents. Procurement control includes provisions for source evaluation and selection, objective esidence of quality furnished by the contractor, surveillance and audit at the source, exandnation of products upon defivery and testing of received material for conformance to procurement criteria. The depth and necessity of procurement controls depend upon the uniqueness and complexity of the item /senice, procurement frequency with the same supplier and past supplier perfonnance for the specific items or senices covered by the )

procurement document. The control of purchased material, equipment and senices is to be in accordance with the requirements of Regulatory Guide 1.38 Rev, 2 (Sn7) and 1.123, Rev.1 (7D7) unless otherwise noted j in Table 1. Paragraph 7.8 of this section provides the controls within this scope for senices obtained from  !

other Entergy Operations Incorporated sites. All other equipment, material and senices will be procured as  !

described in paragraphs 7.1 through 7.7.

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I 7.2 SOURCE EVALUATION AND SELECTICN O 7.2.I V

A Qualified Suppliers List (QSL) is to be maintained and controlled under the direction of the offsite ,

Manager, Material Requirements. The QSL identifies those vendors / contractors that have been evaluated and approved by Material Requirements to furnish material, equipment or senices, and idatifies any restrictions imposed on the vendor / contractor as a result of their evaluation.

1 7.2.2 )

Vendors / Contractors are evaluated and placed on the QSL by any of the following methods, as approved by the Manager, Material Requirements:

(1) Source suney by Material Requirements personnel to verify compliance to applicable 10CFR50, Appendix B requirements or to applicable ASME Section til quality assurance program requirements. ,

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(/ MATERIAL. EOUIPMENT AND SERVICES l

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~(2) Evaluation and acceptance of source surveys performed by others (e.g., NUPIC, other utilities, l

~ NSSS suppliers. and prime contractors) indicating a program meeting the appropriate requirements of 10CFR50, Appendix B.

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(3) A resiew of the vendor's/ contractor's current quality records supported by evidence of l documented qualitative and quantitative information which can be objectively evaluated. This includes review and approval of the vendor's/ contractor's quality assurance program, manual  !

and procedures, when available. j (4) Evaluation of the vendor's/ contractor's history of providing a product / service which performs satisfactorily in actual use. Evaluation information includes: experience of users ofidentical l or similar products / services of the prospective vendor / contractor; and/or procurement records

]

that have been accumulated in connection with previous procurement activities and operating experiences.

(5) In addition to the above, for ASME Code Suppliers, verification that a vendor is a holder of an l l

ASME Certificate of Authorization issued as a result of an ASME suney. j l

7.2.3 l

V )

Vendors / contractors listed on the QSL are to be selected for procurement of material, equipment or services .

cxcept for items designated " commercial-grade" per approved procedures and as noted in paragraph 7.2.4.

1 Standard catalog items may be procured from a vendor / contractor not listed on the QSL provided the ,

l manufacturer of the item is on the QSL and all requested documentation originates from the mamifacturer.

1 The QSL is periodically reviewed and updated per applicable procedures to ensure it is maintained current.

The list of qualified vendors / contractors is available to personnel involved in the procurement process. i 7.2.4 Senices by contractors u hich provide only technical guidance / support or which require work activities to be performed under the scope of this QA Program may be furnished by contractors not listed on the QSL. The contractor's work activities and personnel are to be controlled in accordance with approved procedures to assure that the contractor conforms to the procurement documents.

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7.3 ~ SOURCE SURVEILLANCE AND AUDIT (j 7.3.1 The effectiveness of a vendor's/ contractor's quality assurance program is assessed by Material Requirements personnel at intervals consistent with the importance, complexity, method of receipt and quantity of the products or senices. This assessment may be through source surveillance, source audit, receipt inspection, independent testing or review of source documentation files.

7.3.2 The need for source surveillance / verification is determined by Material Requirements. Source surveillance / verification may also be requested by the originator of the PR/ Contract, or the Quality Organization. Source surveillance is to be performed by Material Requirements personnel or their appointed representative in accordance with surveillance plans approved by the Manager, Material Requirements and the results documented per quality assurance procedures. Reports documenting inspections performed and discrepancies observed are prepared by the person performing the surveillance to document compliance to the procurement documents and for future use as historical quality performance data.

lO

() 7.3.3 Audits of the vendor's/ contractor's quality assurance programs are periodically performed under the direction of the Manager, Material Requirements to verify implementation of a satisfactory quality program on the items or services being procured. Audits performed by others (e.g., NUPIC, other utilities, or prime contractors), as evaluated and approved by the Manager, Material Requirements, may be used as an alternative to audits by Material Requirements personnel to verify the vendor / contractor is implementing a satisfactory quality program. Audits are to be conducted in accordance with Section 18.0 of this manual.

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l 7,4 RECEIPT INSPECTION 7.4.1 a

Materials and equipment, including ASME Code materials and equipment, are subject to inspection upon receipt at ANO. The degree ofinspection is specified in the procurement documents. Receipt inspection is

~

performed in accordance with approved procedures.

7.4.2

_ Receipt inspection activities are to be documented and include, as a ininimum

examination of material or i equipment for shipping damage, proper identification and quantity; and the review of vendor documentation to verify compliance with the procurement document. If a source surveillance has been performed on rnaterial r.nd equipment received at ANO, requirements identified in procurement documents that have been addressed in the Source Surveillance report do not have te be re-verified during receipt.

7.4.3 Vendors are to furnish documentation as required by the procurement documents for objective esidence that f~h .

(j the material or equipment conforms to the procurement requirements. Resiew and acceptance of this documentation is to be performed prior to installation or use of such material or equipment and the results documented unless otherwise specified in approved procedures. Certificates of Conformance may be required by procurement documents which identify the requirements met by the vendor. The validity of the vendor's certification progran is to be periodically venfied through scheduled source surveillance / verification and audit activities or through independent testing of the item by ANO.

7.4.4 Accepted material and equipment is released, identified as to its inspection status and forwarded to a l controlled storage area or released for installation per applicable approved procedures. I 1

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7.4.5 .

() ' Acceptance of services furnished by a contractor is to be identified in the procurement documents. ,

Depending upon the senice performed, acceptance may be by tecimical verification of the data produced, surveillance and/or audit of the activity, or resiew of objective evidence for conformance to the procurement document requirements. The acceptance method is to be performed by qualified individuals knowledgeable in the senice provided.

7.4.6 Independent testing of selected material is to be performed in accordance with approved procedures / instructions to verify conformance to procurement criteria and the validity of the vendor's certification documents.

7.5 NONCONFOPJ4ING ITEMS I

7.5.I l

, Nonconformances identified by the vendor / contractor which adversely affect reliability, performance or

(,/ _ interchangeability of the item and dispositioned repair or use-as-is are to be submitted to and accepted by  ;

1 ANO prior to closure of the nonconformance by the vendor / contractor. These nonconfonnances are to be j documented and become part of the procurement documentation furnished by the vendor / contractor for the material, equipment or senices procured.

l 7.52 i

1 Material and equipment found to be deficient or missing procurement documentation during receising inspection or found to be deficient as a result ofindependent testing are to be clearly identified, segregated from acceptable items and dispositioned per approved procedures and as described in Section 15.0 of this manual.

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() ARKANSAS NUCLEAR ONE SECTION:7.0 CONTROL OF PURCHASED MATERIAL. EQUIPhENT AND SERVICES PAGE 7-5 i

7.6 SPARE PARTS l'

()/ Spare parts are to be purchased to the original design requirements or to those specified by a properly reviewed and approved revision to the design requirements. The applicable quality assurance requirements and documentation requirements for spare parts are to be included in the procurement documents. 1 7.7 STORAGE Material and equipment are to be handled and stored as described in approved procedures and Section 13.0 of this manual.

7.8 SERVICES PROVIDED BY NUCLEAR SITES WITHIN ENTERGY OPERATIONS INCORPORATED (EOI) 7.8.1 SOURCE EVALUATION AND SELECTION 7.8.1.1 A List of Qualified Shared Senices is to be maintained and controlled under the direction of the Director, Nuclear Safety. The list identifies those EOI sites / services that have been evaluated and approved, and identifies any restrictions imposed on the supplying site as a result of the evaluation.

,_ 7.8.1.2 I

V The site providing a senice is evaluated and placed on the List of Qualified Shared Services by any of the following methods, as approved by the Director, Nuclear Safety.

(1) Audit by ANO to verify compliance to applicable 10CFR50, Appendix B and specified quality and technical requirements.

(2) Evaluation and acceptance of audits / assessments performed by others(e.g. other EOI QA groups, Nuclear Safety and Licensing or Assessment groups) indicating a program meeting the appropriate requirements of 10CFR50, Appendix B and specified quality and technical requirements.

(3) A review of the supplying site's current quality records supported by esidence of qualitative and quantitative information which can be objectively evaluated.

(4) Evaluation of the supplying site's history of providing a senice which performs satisfactorily in actual use. Evaluation information includes: experience of users ofidentical or similar senices of  ;

the prospective supplying site; and/or procurement records that have been accumulated in connection with presious procurement activities and operating experiences. j l

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7.8.1.3

. EOl sites listed on the List of Qualified Shared Services are to be selected for procurement of specified j , senices only. The List of Qualified Shared Senices is periodically reviewed and updated per applicable V procedures to ensure it is maintained current. The list of qualified supplying EOl sites is available to personnel involved in the procurement process.

7.8.1.4 l

Senices by EO! sites which provide only technical guidance / support are exempt from the provisions of section 7.8  !

l 7.8.2 SCURCE SURVEILLANCE AND AUDIT 7.8.2.1 The effectiveness of a supplying site's quality assurance program is assessed at intervals consistent with the importance, complexity, method of receipt and quantity of the senices. This assessment may be through  ;

source surveillance, source audit, receipt inspection, assessment or review of source documentation files. l l

7.8.2.2 The need for source surveillance / verification is determined by Quality Assurance or may also be requested by Nuclear Safety and Licensing (Echelon) or the requester of the senice Source surveillance can be performed l by any of the EOl QA Nuclear Safety and Licensing or Assessment personnel in accordance with I surveillance plans approved and documented per their respective programs.  ;

I (O") 7.8.3 RECEIPTINSPECTION 7.8.3.1 Materials and equipment which are part of the senices provided are subject to inspection upon receipt at ANO. The degree ofinspection is specified in the procurement documents Receipt inspection is performed l in accordance with approved procedures.

7.8.3.2 Receipt inspection activities are to be documented and include, as a minimum: examination of material or j equipment for shipping damage, proper identification and quantity; and the review of supplier documentation l to verify compliance with the procurement document. If a source surveillance has been perfonned on material and equipment received at ANO, requirements identified in procurement documents that have been addressed in the Source Surveillance report do not have to be re-verified during receipt.

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7.8.3.3 Supplying site's are to furnish documentation as required by the procurement documents for objective l,- evidence that the material or equipment confonns to the procurement requirements. Resiew and acceptance

\- of this documentation is to be performed prior to installation or use of such material or equipment and the results documented unless otherwise specified in approved procedures. Certificates of Conformance may be required by procurement documents which identify the requirements met by the supplier. The validity of the supplying site's certification program is to be periodically verified through scheduled source surveillance / verification and audit activities or through independent testing of the item by ANO.

7.8.3.4 Accepted material and equipment are released, identified as to their inspection status and fonvarded to a controlled storage area or released for installation /use per applicable approved procedures.

7.8.3.5 Acceptance methods for sen-ices furnished by a supplying site are to be identified in the procurement I documents. Depending upon the senice performed, acceptance maybe by technical verification of the data produced, surveillance and/or audit of the activity, or review of objective evidence for conformance to the i

procurement requirements. The acceptance method is to be perfonned by qualified individuals knowledgeable 1 in the senice provided. I 7.8.4 NON-CONFORMING ITEMS l

7.8.4.1 i Material and equipment found to be deficient or missing procurement documentation during receiving l

.g inspection are to be clearly identified, segregated from acceptable items and dispositioned per approved  !

procedures and as described in Section 15.0 of this manual.

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1 7.8.5 STORAGE 7.8.5.1 Material and equipment are to be handled and stored as described in approved procedures and Section 13.0 of this manual.

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8.0 IDENTIFICATION AND CONTROL OF MATERIALS. PARTS AND COMPONENTS i

1 Q(~'N I

8.1 SCOPE i

8.1.1 J

Measures for the identification and control of materials (including consumables), parts and components, including partially fabricated subassemblies, are to be established within approved procedures. These procedures are to relate an item of production (batch, component, part, etc.) at any stage, from initial receipt through fabrication, installation, repair or modification to an applicable drawing specification or other i pertinent tecimical documents. These measures are to assure that only correct and accepted items are used and installed.

8.1.2 Methods for the traceability of materials, parts and components to specific inspection and test records, when required by codes, standards, specifications or procurement documents, are to be established within approved  ;

1 procedures and maintained throughout the life or consumption of the item. l I

'A 3, j 8.2 IDENTIFICATION 8.2.I Materials, parts and components are to be identified by the vendor in accordance with the applicable design standards, codes and/or instructions specified in the procurement documents.

8.2.2 Materials, parts and components are to be identified and/or tagged at the plant in accordance with applicable approved procedures. These tags identify the status of and provide traceability to the item throughout storage and release for installation.

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8.2.3 X

(,). Identification of materials, parts and components is accomplished by either marking or tagging on the item or through records traceable to the item.

8.2.3.1 Physical identification is to be used to the maximum extent possible. Where physical identification is either impractical or insufficient, physical separation, procedural controls or other appropriate means are to be employed in accordance with approved procedures.

8.2.3.2 When identification markings are employed, the markings are to be clear, unambiguous and indelible and applied in such a manner as not to affect the integrity or function of the item. Markings are also to be transferred to each piece of material (plate, barstock, tubing, etc.) when subdivided. Large quantities of small items may be identified by applying markings or tags to their shipping packages, boxes or other suitable containers.

O V 8.2.3.3 Identification markings are to be recorded on records or as-built documents if current markings are to be hidden or subject to obliteration by surface treatment or coatings during fabrication, installation, repair or modifications.

8.3 CONTROL Plant organizations receiving materials, parts and components are to verify that they are properly identified while under their control. Quality audit, surveillance and inspection activities ensure compliance to requirements and also ensure that materials, parts, and components are being identified in accordance with this mamial.

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("/ CONTROL OF MATERIALS, PARTS AND COMPONENTS l

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8.4 DEFECTIVE ORINCORRECT ITEMS r

() 8.4.1 Defective or incorrect materials, parts and compeents identified by plant personnel or support groups are to be handled in accordance with Section 15.0 of this manual and approved procedures for nonconformances and corrective action. Defective or incorrect items are to be tagged with a " hold tag" aflixed to the item or othenvise identified per approved procedures.

8.4.2.

Defective or incorrect items are to be stored in segregated areas except for those items installed or which, due to their size, weight configuration, etc., are impractical or impossible to store in the designated controlled storage area.

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ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS N ARKANSAS NUCLEAR ONE SECTION: 8.0 IDENTIFICATION AND PAGE 8-3

~( CONTROL OF MATERIALS, PARTS AND COMPONENTS

. 9.0 CONTROL OF SPECIAL PROCESSES

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) 9.1 SCOPE Special processes are to be controlled through the use of qualified personnel and approved procedures which meet the requirements of applicable codes, specifications, standards and other criteria stipulated in ANO licensing documents.

9.2 GENERAL 9.2.I Special processes are those activities which require interim in-process controls in addition to final inspection to ensure quality and include such activities as welding, nondestmetive examination, heat treating, coating, plating and chemical cleaning.  ;

I 9.2.2 Technically qualified personnel are to establish the procedural and qualification requirements for those special j I processes not covered by existing codes or standards or where the QA Program requirements exceed the requirements of established codes or standards. ,

1 9.2.3 l

The requirements for welding and nondestructive examination are to comply with the applicable portions of the ASME Boiler and Pressure Vessel Code or for structural welds, the AWS Structural Steel Code DI.1, and the American Society of Nondestructive Testing Recommended Practices (SNT-TC-1 A and supplements).

The requirements for cleaning and flushing of fluid systems are to comply with the requirements of NRC Regulatory Guide 1.37, dated 3/16/73 unless otherwise noted in Table 1. l l

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1 ENTERGY QA MANUAL OPERATIONS REV. 20 i p OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 9.0 CONTROL OF SPECIAL PAGE 9-1 (f PROCESSES

9.3 QUALIFICATION im

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9.3.1 Special process procedures for welding and nondestructive examinations are to be qualified prior to use to ensure compliance with applicable codes, standards or specifications. These qualifications are to be documented and also made available for resiew to the Code Inspector for activities on ASME items.

9.3.2 Personnel responsible for the performance and verification of special processes are to be qualified and/or certified according to applicable codes, standards, specifications, regulatory guides and approved procedures.

These qualifications and certifications are to be documented and made available for resiew to the Code Inspector for activities on ASME items. Personnel qualification and/or certification records for a special process are to be regularly reviewed by the supenisor responsible for that special process to ensure that the appropriate documents are up-to-date and personnel are periodically re-qualified and/or re-certified in accordance with approved procedures.

9.4 RECORDS O

V The results of special processes are to be documented, reviewed, approved and stored in accordance with appropriate approved procedures and as addressed in other sections of this manual.

9.5 VERIFICATION Perfonnance of special processes in accordance with applicable codes, standards, specifications and approved procedures is verified by Quality personnel through performance of their audit, review, surveillance and inspection activities.

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y/ ARKANSAS NUCLEAR ONE SECTION: 9.0 CONTROL OF SPECIAL PAGE 9-2 PROCESSES

10.0 INSPECTION l

( / 10.1 SCOPE ~

Inspections relating to normal operating activities and inspections relating to operating actisities comparable in nature and extent to those occurring during initial plant design and constniction are to be controlled to assure that inspections are performed in accordance with applicable design documents, codes, standctds, specifications and procedures. Inspection activities are to be in accordance with Regulatory Guide 1.33, Rev. 2 (208), unless otherwise noted in Table 1.

'10.2 GENERAL 10.2.1 Inspection activities relating to normal operating activities (Operational Inspections) include:

(1) Work functions associated with normal operation of the plant (2) Routine maintenance (3) Technical senices routinely assigned to the on-site operating organization O (4) Non-routine maintenance activities and minor modifications made by the on-site operating organization that are not comparable in nature and extent to related activities occurring during initial plant design and construction l

10.2.2 l

Inspection activities relating to operating activities comparable in nature and extent to related actisities  !

occurring during design and construction (Construction Inspections) include:

1) Non-routine maintenance, except as noted in paragraph 10.2.1 l

2) Modifications, except as noted in paragraph 10.2.1 The following Regulatory Guides are to be applied, as applicable, in determining the basis for required construction inspections: R.G.1.30, Rev. 0 (8/72); R.G.1.37, (3n3); R.G.1.38, Rev. 2 (507); R.G.1.39, Rev. 2 (907); R.G.1.94, Rev.1 (4n6); and R.G.1.116, Rev 0-R (6n6).

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10.2.3 l,b V

- Personnel performing inspection activities to verify quality are to be qualified as stated in Section 2.0 of this manual. When inspection techniques require specialized qualifications or skills, personnel performing the inspection are to meet applicable licensing requirements, codes and standards appropriate to the discipline involved.

-10.3 CONTROL OF INSPECTIONS 10.3.1 l

Inspections are to be performed in accordance with approved written instructions or procedures, which set forth  ;

1 the requirements and acceptance limits and specify the inspection responsibilities. Ifinspections reqmre ,

detailed written procedures to perform the task, the procedures are to contain, as a minimum, the following:

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(1) Qualitative and/or quantitative acceptance criteria (2) Prerequisites for performing the inspection and any limiting conditions (3) Identification of any special equipment and tools required to perform the inspection (when l accuracy requirements for inspections exceed the accuracy of normally available process or b measuring and test equipment, such additional accuracy requirements are to be specified within those inspection procedures)

-(4) A step-by-step description of the method ofinspection, examination, measurement or test to be  !

l performed l (5) Identification of those inspection results to be documented. Inspection forms or checklists are to be used as an aid in documenting the inspection activity to assure quality requirements have been met 10.3.2 Operational inspections are to be performed by qualified individuals other than those who performed or directly L supervised the activity being inspected. Construction inspections are to be performed by qualified individuals other than those who performed or directly supervised the activity being inspected and do not report directly to l the immediate supenisors who are responsible for the activity being inspected.

L r~% ' ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 10.0 INSPECTION PAGE 10-2 l

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10.3.2.1 h-v Operational inspections may be performed by second-line supenisory personnel or by other qualified personnel not assigned first-line supenisory responsibility for conduct of the work.

i 10.3.2.2 Construction inspections are to be conducted in a manner similar to that associated with construction phase activities in accordance with applicable approved procedures.

10.3.2.3 Ifindividuals performing inspections are not part of the ANO Organization, the inspection procedures, personnel qualification criteria, and independence from undue pressure such as cost and schedule are to be reviewed and found acceptable by the Director, Nuclear Safety or designee prior to initiation of the actisity.

10.3.3 j If an inspection determined to be required is impossible or disadvantageous, indirect cor' o' S wa. coring processing methods, equipment and personnel is to be provided to verify conformance wit' w.able h]'

\

documented instructions, procedures and drawings. Both inspection and process monitoring are to be provided when control is inadequate without both.

I 10.4 INSPECTION POINTS l l

l 10.4.1-  ;

I Inspection hold points are established within non-routine maintenance procedures and Plant Modification I Packages (PMPs) by Engineering and reviewed by Quality Cor.rol personnel for concurrence and possible j assignment of additional inspection hold points to further assure conformance with applicable instnictions, procedures, drawings and related documents or to meet appropriate code and regulatory requirements.

Inspection hold points for work functions associated with activities other than non-routine malatenance and PMPs are established by the originating department, Quality personnel or other responsible individuals and resiewed by Quality Control personnel for concurrence and possible assignment of additional inspection hold points.

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i Work is not to proceed past a designated inspection hold point until signed by a qualified inspector or waived, l j

,s in writing, by the Director, Nuclear Safety or designee.

V.

10.4.2 l

Inspection hold points are inserted in procedures based upon safety significance, complexity of the item or activity, degree of standardization of the item or activity, past performance of the item or activity and the ability to verify quality by job-site testing.

10.4.3 Inspection responsibilities, requirements, information and acceptance criteria for the work activity are to be identified in appropriate, approved documents (e.g., procedures, checklists). l 10.4.4 For work involdng the modification, repair, replacement or inservice inspection of ASME Code materials, pans and components, the work packages are to be made available to the Code Inspector prior to conunencing work for his review and assignment ofinspection hold points. The department responsible for the work activity f

is responsible for notifying the Code Inspector when the hold point is reached. Work is not to proceed past a Code Inspector's inspection hold point until signed or waived by the Code Inspector.

10.5 DOCUMEWATION 10.5.1 Inspections and process monitoring activities are to be performed and the results docmnented in accordance with approved procedures or instructions. Records are to: provide objective evidence that the inspections and monitoring activities were performed in compliance with procedures, instructions or drawings to verify design requirements; show compliance with acceptance criteria or identify the cause of rejected items; and identify the appropriate inspection personnel approving the results.

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L 10.5.2 Records are to be maintained in accordance with approved procedures and Section 17.0 of this manual.

Inspection results on ASME Code items are available to the Code Inspector for his review.

10.5.3 l

l The results ofinspection and monitoring activities are periodically evaluated per approved procedures and the results documented to detennine whether the individual inspection programs demonstrate that the plant can be

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operated safely and as designed.

10.6 NONCONFORMANCES

Nonconforming items found as a result ofinspection and monitoring activities are identified, segregated and

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dispositioned in accordance with approved written procedures and Section 15.0 of this manual. Rework, repair l

or replacement performed after completion ofinspections requires re-inspection to the extent necessary to determine acceptability to established criteria.

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11.0 TEST CONTROL (n ' 11.1 SCOPE A test program is to be established to assure that testing required to demonstrate that an item will perform satisfactorily in service is identified, documented and performed in accordance with written test procedures.

These procedures are to incorporate or reference the requirements and acceptance criteria contained in applicable codes, standards and specifications and in the licensing documents. These activities include testing during the operational phases of the plant and those tests required as a result of modifications, repairs or maintenance. These activities are also to comply with the applicable provisions of Regulatory Guide 1.33, Rev.

2, unless otherwise noted in Table 1, and with the applicable sections of the ASME Boiler and Pressure Vessel Code for ASME-designated items.

I1.2 PROCEDURES 11.2.1 Written procedures / instructions are to be prepared to describe the requirements for conduct of the testing activities. These procedures / instructions are to contain or reference the information required in Section 5.0 of this manual and in the applicable Regulatory Guides pertaining to quality assurance requirements for testing activities.

I1.2.2 .

Test procedures / instructions and revisions thereto are to be subject to the same review and approval process as l outlined in Section 5.0 of this manual. l l

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11.3 TEST CONTROLS j

QQ l1.3.1 l

Tests relating to plant start-up following a unit shutdown or fuel loading are to be conducted per written procedures / instructions in order to evaluate plant performance as the start-up progresses. Initial start-up test programs are to be planned to permit safe fuel loading and start-up, to increase power in safe increments and to perform major testing at specified power plateaus.

11.3.2 Surveillance tests during the operational phase of the plant are to be conducted per written procedures /instmetions to assure that failures or substandard performances do not remain undetected and that the required operability is maintained to ensure they will continue to operate, keeping parameters within normal bounds, or will act to put the plant in a safe condition if they exceed normal bounds.

I1.3.2.1

.g Mandatory in-plant surveillance tests and inspections required to assure operation within the limiting conditions of operation are identified in the SAR and Technical Specifications applicable to each unit. To ensure that the required tests are performed as scheduled within the specified time interval, sun eillance procedures are established and maintained for mandatory surveillances identified in the SAR and Technical Specifications.

These procedures are to specify the component or system, type of surveillance activity, frequency of actisity and the cognizant individual responsible for completion of the surveillance actisity.

I1.3.2.2 Insenice inspections required to meet the requirements of ASME Boiler and Pressure Vessel Code,Section XI, are to be identified in the Insenice Inspection (ISI) Programs applicable to each unit. Engineering Programs is to establish and maintain an ISI plan for each unit. The plan specifies the inspection items, inspection procedures, inspection intervals and types ofinspections. Engineering Programs is to coordinate the implementation of the ISI plans at appropriate scheduled outages. The plans are also to be made available for review by the Code Inspector.

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I 11.3.3 l

(. Tests following plant modifications, repairs, maintenrnce or significant changes in operating procedures are to be conducted to confirm that they are not detrimental to the safe and efficient operation of the plant and that the components or systems demonstrate satisfactory performance.

11.3.4 Requirements for the given test to be performn < e to be identified in the test procedures /instnictions. Evidence 4

is to be available to assure the following min ' iequirements are met:

4 (1) Test equipment and measuring devices are calibrated in accordance with the requirements of Section 12.0 of this manual and are functioning properly. j (2) Test personnel have been qualified to perform the test in accordance with the requirements of Section 2.0 of this manual.

(3) Appropriate witness and hold point notifications have been prosided.

(4) Test prercquisites are comp!

ted.

(5) When accuracy requirements for tests exceed the accuracy of normally available process or measuring and test equipment, such additional accuracy requirements are to be specified within l those test procedures.

I1.3.5

• Testing activities are to be subject to surveillance / inspections in accordance with Section 10.0 of this manual.

Testing as a result of repairs, modifications, replacement or scheduled insenice ter.ts on ASME Code items is also subject to inspection by the Code Inspector. The assignment ofinspection hold points is described in Section 10.0 of this manual.

I1.3.6 Test results are to be documented in accordance with the applicable procedures /instnictions. Test documents are to contain at least the following:

(1) Identity ofitem tested ,

(2) Date of test (3) As-found condition i

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1 (4) Identification ofindividuals performing test 1 (5) Test results 7

I (6) Corrective actions perform xt, if any (7) As-left condition 4

. I1.3.7

(

Test results are to be evaluated by responsible, qualified personnel per approved procedures to assure that test d

objectives and inspection requirements have been satisified. Nonconforming items are to be identified and controlled in accordance with Section 15.0 of this manual.

11.4- RECORDS Test results are to provide objective evidence that the testing was performed in compliance with approved procedures. Test records are to be maintained and transmitted to the Document Control Center for retention in accordance with Section 17.0 of this manual.

11.5 TEST STATUS Inspection and test status is to be controlled in accordance with the provisions of Section 14.0 of this manual.

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12.0 CONTROL OF MEASURING AND TEST EOUIPMENT

'N j 12.1 SCOPE 12.1.1 A program is established to assure that desices used for measurements, tests and calibrations are identified, controlled and calibrated against reference standards to assure that accuracy is maintained within the limits specified by the inspection or test requirements. Control of measuring and test equipment is to comply with the applicable prosisions of Regulatory Guide 1.33, Rev. 2, pertaining to measuring and test equipment, unless otherwise noted in Table 1.

12.1.2 This section is generally applicable to chemical and radiochemical equipment, except for paragraphs 12.3.3, 12.3.4 and 12.4.2. The controls for the calibration of chemical and radicchemical measuring equipment are to comply with the prosisions of Regulatory Guide 1.33, Rev. 2, Appendix A, Section 10.0, and performed in accordance with chemical and radiochemical control procedures.

()

A 12.1.3 This section does not apply to rulers, tape measures, levels or other such devices w here normal commercial practices provide adequate accuracy.

12.2 RESPONSIBILITIES 12.2.1 The cognizant superintendents / group supenisors are responsible for establishing and maintaining lists of l 1

measuring and test equipment under their control that require periodic calibration and for the calibration of this equipment, as assigned within approved procedures.

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4 12.2.2 s

The cognizant supenisor is responsible for identifying measuring and test equipment required for the actisity j

and assures that the desices are used only oy qualified personnel.

12.2.3 Personnel performing the activity are responsible for utilizing only properly identified and calibrated )

measuring and test equipment when performing inspections and tests for record.

I 12.2.4 '

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The Quality Organization is responsible for monitoring test equipment control and use in order to verify compliance with the program.

12.3 GENERAL 12.3.1 Calibration requirements are to be established for each type of measuring and test equipment. These requirements are to conform to recognized codes and standards and to local, state ard federal regulations and are to be referenced on the calibration reports / logs. Published standard practices, wTitten instructions that accompany purchased equipment, site generated procedures or other acceptable instructions may be used for calibration of M&TE upon documented approval of M&TE management.

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1 12.3.2 Measuring and test equipment are to be properly controlled, calibrated and adjusted at specific intenals or prior to use to assure the necessary accuracy of calibrated equipment. Calibration inten'als are to bc based upon the type of equipment, manufacturer's recommendations, stability and reliability characteristics, required accuracies, use and other conditions affecting calibration.

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12.3.3 G

Reference standards used in the calibration of measuring and test equipment are to be traceable to the National Institute of Standards and Technology, or if nonexistent, to accepted industry or ANO standards. Reference standards are to have an accuracy at least four times that of the measuring and test equipment. In any instance i where the four times criteria is unable to be met, standards are to have im accuracy level, acceptable calibration range and precision equal to or better than those required for the ranges affected by the calibration.

Accuracies less than four times will be acceptable when warranted by statistical analysis or limited by the state-of-the-art as authorized by responsible management. Reference standards are to be maintained in an emironment with temperature, humidity and cleanliness controls compatible with maintaining accuracy and operating characteristics of the standards.

12.3.4  :

When measuring and test equipment are found to be out of calibration, an evaluation of the validity of prnious  !

inspection or test results and the acceptability ofitems previously inspected or tested is to be made and documented by written report in accordance with approved procedures. If any piece of measuring or test equipment is consistently found to be out of calibration, it is to be repaired or replaced.

m 12.3.5 l

l Re-calibration per approved procedures is to be performed when the accuracy of either installed or calibrated equipment is questionable.

12.4 EQUIPMENTIDENTIFICATION 12.4.1 )

l Measuring and test equipment lists are to contain sufficient information to uniquely identify each item listed J and is to include, as a minimum, calibration intervals, tolerances and storage locations. The lists are also to identify the group responsible for the control of each item. j l

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-12.4.2

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- () - Items listed on measuring and test equipment lists are to be tagged, labeled or otherwise identified per approved procedures in such a manner that clearly identifies the equipment and their calibration status and provides traceability to the calibration records.

12.4.3 Measuring and test equipment found to be out of calibration are to be tagged and segregated from acceptable equipment in accordance with approved procedures until repaired and/or re-calibrated.

12.5 RECORDS Calibration documentation is to be maintained to verify calibration status, condition, accuracy and out-of-tolerance trends of the equipment.

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13.0 HANDLING STORAGE AND SHIPPING

- tN Q 13.1 SCOPE Activities for the handling, storage and shipping, including cleaning, packaging and preservation of materials f

and equipment are to be performed in accordance with established instructions, procedures or drawings, to prevent damage, deterioration or loss of the item. Activities are to comply with the provisions of Regulatory Guide 1.38, Rev. 2, unless otherwise noted in Table 1, 13.2 GENERAL l

13.2.1 l

1 Instructions for preservation are to be provided for items subject to deterioration or damage through exposure to air, moisture or other emironments during fabrication, processing, assembly and interim storage periods. Items I 1

are to be cleaned, preserved and packaged as required to preclude deterioration and prevent damage. When maintenance of specific internal or external emironments is necessary, it is to be included in special packaging instructions and maintenance procedures.

i

) 13.2.2 Procurement documents assure that any special cleaning, presening, handling, packaging or shipping requirements for purchased material or equipment are taken into account.

1 13.2.3 For critical, sensitive, perishable or high value articles, recommendations for their handling, storage, packaging, shipping and presen ation are to be requested from the supplier per the procurement documents and fr.rnished to the plant prior to or upon receipt of the items at the plant.

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13.3 SHIPPING CONTROLS Lb gi 13.3 1 Shipping requirements are to be specified in the procurement documents. Suppliers' compliance with these l requirements are to include controls to assure that items are complete and assembled as required; items have been preserved and packaged in accordance with the procurement documents; items have been marked and identified in accordance with specifications and procurement documet.ts; items have been loaded for shipment in such a marmer as to prevent damage; and required documentation is complete and furnished in accordance with the procurement documents 13.3.2 l

Special nuclear material and sources are to be shipped and stored as specified in the operating licenses and other appropriate regulatory documents. The Manager, Radiation Protection / Chemistry is responsible for assuring that radioactive sources and instruments containing radioactive sources are stored and handled per these requirements and approved procedures. The Manager, Radiation Protection / Chemistry is also responsible for assuring that low-level waste material is stored and shipped per these requirements and approved procedures.

The Managers, System Engineering, ANO-1 & 2 are responsible for assuring that special nuclear material

) (SNM), as defined in approved procedures, is shipped, stored and handled per these requirements and the approved procedures.

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13.4 RECEIVING 13.4.1 Materials and equipment are to be received at the plant per approved procedures and subjected to a receipt inspection in accordance with Section 7.0 of this manual. As part of the inspection activity, received materials and equipment are to be inspected for damage, deterioration, cleanliness and proper identification and markings

. per approved procedures for receipt inspection.

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13.4.2 e

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j,] Results of the receiving inspection and disposition of the material or equipment are to be documented on receiving inspection records. Nonconforming items are to be handled in accordance with approved procedures and Section 15.0 of this manual.

13.5 STORAGE CONTROLS 13.5.1 Materials and equipment which have completed the receiving process are to be stored based on the classification level of storage specified on the procurement documents or related design documents.

13.5.2 Storage control procedures are to be established which include, as a minimum, provisions for the following:

controlled access and usage of the storage area; cleanliness and good housekeeping controls; fire protection; protection from emironmental hazards; segregation of hazardous materials; and control of those items which have a specified shelflife.

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. V) 13.5.3 Only items which have completed the receiving process are to be placed in a controlled storage area. Records of the items' location (s) are to be provided by the Manager, Materials Purchasing and Contracts (see paragraph 13.3.2 for control of radioactive sources, low-level waste material and SNM) to identify those items currently in storage and to facilitate inspection and maintenance planning. Issuance ofitems from storage for installation or use is to be documented and controlled in accordance with approved procedures.

13.5.4 Items identified as requiring maintenance during storage are to be maintained in accordance with a documented maintenance program.

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13.5.5 Storage areas are to be monitored by individuals responsible for the storage areas so that the integrity and security of stored items are effectively maintained. Inspections and examinations under the control of the Supenisor, Quality Control are to be perfonned and documented on a periodic basis to assure that the integrity of the items and their containers is being maintained. Periodic audits under the control of the Supenisor(s),

Quality Assurance are also performed to assure compliance with storage requirements.

13.6 HANDLING CONTROLS 13.6.1 Special handling requirements are to be speciEed in the procurement documents and approved procedures to protect the quality ofitems susceptible to handling damage. Special tools and equipment are to be prosided to handle these items and are to be controlled and maintained per written procedure to assure safe and adequate handling.

13.6.2 Special handling tools and equipment are to be inspected and tested at specific times in accordance with written

( procedures to verify that the handling tools and equipment are adequately maintained. Inspection and test status of these handling tools and equipment are to be controlled in accordance with the applicable sections of this manual. '

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14.0 INSPECTION. TEST AND OPERATING STATUS

/N SCOPE

(] 14.1 14.1.1 The removal from senice, inprocess status and return to senice of equipment, components and systems for maintenance, modifications, repair, test or inspection is to be controlled per approved procedures.

These controls are to assure that plant personnel are aware of equipment, structure or system conditions and to prevent their inadvertent use unless cleared by Operations personnel.

14.1.2 Maintenance activities are to be performed in accordance with an established maintenance program to assure that equipment, systems and structures are maintained in a condition which allows them to perfonn their intended function.

14.2 EQUIPMENT CONTROL q l4.2.1 Prior to removal of equipment, components or systems from senice for maintenance, modification, repair, test or inspection activities, permission is to be received and documented from the appropriate Operations Supenision. Operations Supenision is to assure that the item can be released without affecting plant safety.

14.2.2 The status of equipment, components and systems during these activities is to be identified in accordance with approved procedures / instructions, which contain, as a minimum, the following:

(1) Methods for control of equipment to maintain personnel and reactor safety and to avoid unauthorized operation of equipment or systems I

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 14.0 INSPECTION, TEST AND PAGE 14-1 O'- OPERATING STATUS e

(2) The t se of markings or other suitable means to indicate the status of activities being performed upon individual items (Suitable means are to include identification numbers which are traceable to records or to the status of these actisities.) ,

(3) Provisions for the identification ofitems which have satisfactorily passed the required nctivities (In cases where required documentary evidence is not available, the associated equipment or system is to be considered nonconforming and handled in accordance with Section 15.0 of this manual.)

(4) Provisions for independent verifications to ensure that necessary measures (locking or tagging) to secure and identify equipment or systems in a controlled status have been implemented correctly 14.2.3 When entry into a closed system is required, control measures are to be established to prevent entry of extraneous material and to assure that foreign material is removed before the system is reclosed.

14.2.4 O

During maintenance or modification activities, certain portions of systems, as identified in approved procedures, may be subject to potential contamination with foreign materials. To prevent such contamination, control measures, including measures for access control, are to be established. l l

Immediately prior to closure, an inspection is to be conducted to assure cleanliness and the result of such  !

inspection is to be documented.

14.2.5 If temporary modifications (such as temporary bypass lines, electrical jumpers, lifted electrical leads and temporaq trip point settings) are required for a system or piece of equipment, they are to be perfonned in accordance with approved procedures. Procedures that control such temporary modifications shall delineate reruirements to:

3 ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS pI 1 ARKANSAS NUCLEAR ONE SECTION: 14.0 INSPECTION, TEST AND PAGE 14-2 OPERATING STATUS 4

(1) Maintain appropriite status logs of temporary modifications (2) Perform independent verification of temporary modifications, by an individual cognizant of the purpose and effect of the temporary modification (3) Document temporary modifications to assure the required actions are taken to return the equipment or system to its original operating configuration and status Additiontily, temporary modifications which constitute temporary changes to plant configuration due to routine tasks such as additions of temporaryjumpers or gauges as part of maintenance, calibration, or troubleshooting, may be installed and removed by use of approved procedures or work pla is, providing (2) and (3) above are satisfied. These changes are not maintained on a status log since removsl of the temporary change is controlled by the same procedure or work plan which installed it.

14.2.6 When equipment or a sysicm is properly identified as being ready to be returned to service, the appropriate Operations Supervision is notified and initiates the proper operation procedures. Testing of the equipment or system for functional acceptability is to be in accordance with Section 11.0 of this manual and documented to lO Verify current status of the item.

14.2.7 Equipment, structures and systems found to be nonconforming as a result of an activity are to be handled in accordance with approved procedures and Section 15.0 of this manual.

14.3 MAINTENANCE CONTROL 14.3.1 i-In addition to the requirements and controls identified in subsection 14.2 of this manual, a maintenance program is to be planned and scheduled through the appropriate Manager, Maintenance to assure that the safety of the plant is not compromised nor the Technical Specifications violated. Maintenance activities are to be performed per approved procedures and instructions and conducted in a manner to asrure quality at least ENTERGY QA MANUAL OPERATIONS REV. 20 g '

OPERATIONS

( ARKANSAS NUCLEAR ONE SECTION: 14.0 INSPECTION, TEST AND PAGE 14-3 OPERATING STATUS

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i J

equivalent to that specified in the design documents, material specifications and inspection requirements. As experience is gained in operation of the plant, routine maintenance may be altered to improve equipment

O

, ., performance and procedures for repair of equipment are to be improved as directed by the appropriate Manager, l

i 4 Maintenance. i I

4 14.3.2

, A preventive maintenance program, including procedures and instructions for systems, structurcs and j i components, is to be ,;stablished and maintained, which prescribes the frequency and type of maintenance to be perfonned in order to preclude equipment malfunctions. The preventive maintenance program requirements, including associated procedures and task instmetions will be maintained by the appropriate Manager, Maintenance as applicable based on the specific maintenance discipline. The associated engineering evaluations for each unit will be maintained under the applicable Manager, Maintenance. Implementation of

! the program is the responsibility of the General Manager, Plant Operations and is implemented by qualified maintenance personnel in accordance with approved procedures and instructions which specify the work

{ j activities, acceptance requirements and the control measures to assure adequate quality. When equipment 2

malfunctions occur, the cause is to be promptly determined, evaluated and recorded per approved procedures  ;

} and Section 16.0 of this manual.

j 14.4 OVERALL PLANT STATUS 4

_O 14.4.1 The Superintendents, Shift Operations are provided sufficient knowledge of the overall plant status of equipment, structures and systems to control operation of the plant in a safe manner. The shift operators are to maintain a ready reference of plant systems, equipment and component aligmnents, as well as a status board summary of their conditions.

14.4.2 The turnover of duties to personnel on succeeding shifts is conducted in accordance with approved procedures.

These procedures include documented turnover action appropnate to the duty station acknowledging the status of the nuclear power plant, its structures, systems and components (including design changes / modifications  !

which may affect the performance of their duties) and transfer of authority.

ENTERGY QA MANUAL OPERATIONS REV. 20 p OPERATIONS g ARKANSAS NUCLEAR ONE SECTION: 14.0 INSPECTION, TEST AND OPERATING STATUS PAGE 14-4

15.0 NONCONFORMING MATERIAL. PARTS AND COMPONENTS 15.1 SCOPE

/g\ -  ;

, Nc,nconfonning items are to include materials, parts, components and, as applicable, senices (including l l- computer codes) that do not conform to applicable regulations, codes, standards, specifications, drawings  !

. or licensing documents. Nonconforming items are to be controlled in accordance with approved j procedures to prevent their inadvertent use or installation. These procedures are to contain measures to ,

' 1 assure the prompt identification and notification, documentation, segregation, technical resiew and  !

disposition of a nonconfonning item. 1 1

15.2 GENERAL l

15.2.1 it is the responsibility of each individual to identify a nonconformance and to report it to their cognizant k supenisor for review and concurrence. The initiator is to document the nonconformance as identified I within approved procedures. If the nonconformance is determined to be a Technical Specification violation and/or reportable to the NRC, see subsection 16.5.

15.2.2

[%)i Nonconforming items are to be identified by tagging, marking or as otherwise identified per approved procedures to control further processing or, when physical segregation is not practical, to prevent inadvertent use or installation of the item. Nonconforming items are to be segregated from acceptable items unless they are currently installed or their size, weight, configuration, etc., makes it impractical to move to a segregated area. Tags and/or markings are to remain on the item until the disposition is complete per approved procedures.

15.2.3 Reports of nonconforming items are to identify the group responsible for dispositioning the nonconformance. The assigned individual within the responsible group is to evaluate the I

nonconformance and confer, as appropriate, with interfacing groups to determine a recommended disposition. The disposition for materials, parts, components and as applicable, senices (including )

computer codes), which may be reject, rework, repair or use-as-is, and any actions taken/ required to be taken as a result of the disposition are to be documented on the report.

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ARKANSAS NUCLEAR ONE SECTION:15.0 NONCONFORMING PAGE 15-1 MATERIAL PARTS AND COMPONENTS 1

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15.2.4 NN Q- Review of the disposition for concurrence is to be performed by th: individual / group identified within approved procedures. If the resiew group or individual cannot agree with the assigned individual on the disposition, either the General Manager, Plant Operations or the appropriate Director or Manager, is to decide. For a repair or use-as-is disposition, a cognizant individual knowledgeable in the design requirements for the afTected item is also to resiew the report for concurrence of the disposition. Written justification for the design change, repair or deviation that has been axepted is to be documented to denote the as-built condition and is to be made a part of the report.

15.2.5 The acceptability of rework or repair of materials, parts, components, systems and structures is to be verified by re-inspecting the item as originally inspected or by a method which is at least equal to the original inspection method. The rework and repair inspection records are to be documented and become part of the permanent records for the item.

15.2.6 h

.G Upon completion of the disposition, the nonconformance repor'. is to receive an independent resiew in acco: dance with approved procedures, for concurrence or posnble assignment of additional actions pertaining to the disposition.

'15.2.7 l

For ASME Code,Section III, Division 1 materials, parts and components dispositioned repair or use-as-is, the nonconformance report is to be subject to review and concurrence by the Code Inspector, i

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r

~ 15.3 SUPPLIER NONCONFORMANCES 15.3.1 i

Procurement documents are to contain requirements for the vendor / contractor to identify to ANO those  ;

items which violate a technical or material requirement of the procurement document and which results in a disposition of repair or use-as-is. All such nonconformances are to be reported to ANO for ,

evaluation and acceptance. The vendor / contractor is to document such nonconformances on its applicable nonconformance report which is to be included in the final documentation package submitted to ANO, in accordance wi'.h the procurement documents.

15.3.2 Upon receipt ofitems at the plant, ANO Receipt Inspection personnel are to review any nonconformance reports in the documentation package to ensure the nonconforming items have been properly dispositioned and accepted by ANO.

15.4 RECORDS O

Q 15.4.1 +

Upon completion of disposition and verification activities, the completed nonconformance report, and related documents generated to ensure proper disposition and resolution of the nonconformance, are to be _

forwarded to and maintained by the Document Control Center.

15.5 DEFICIENCY TRENDING The Director, Nuclear Safety or designee is to maintain and issue a trending report, at least quarterly, of nonconformances to the Vice President, Operations .ANO for resiew.

ENTERGY QA MANUAL OPERATIONS REV. 20 i OPERATIONS ARKANSAS NUCLEAR ONE SECTION: 15.0 NONCONFORMING PAGE 15-3 MATERIAL PARTS AND COMPONENTS i

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16.0 CORRECTIVE ACTION

()

i 16.1 SCOPE A corrective action system is established to assure that conditions adverse to plant safety, such as failures, malfunctions, deficiencies, deviations, defective materials and equipment, and nonconformances are promptly identified and corrected. In the case of significant conditions adverse to safety, this system is to assure that the cause of the condition is determined and corrective action taken is documented and reported to appropriate levels of management for independent resiew.

16.2 GENERAL 16.2.1 When deviations, deficiencies, malfunctions, nonconformances or other conditions are encountered, they are to be reported to responsible authorities for review and disposition in accordance with approved procedures.

16.2.2

(~~N t Cognizant supenisors are to review discrepancies discovered during the course of plant operations and take appropriate action to resolve the discrepancies. For significant conditions adverse to safety, they are to initiate action to identify their root causes and take necessaiy corrective action to preclude repetition.

16.2.3 Evaluation of the corrective action is to be performed by the individual / group identified within approved procedures to determine its adequacy and completeness and to assure the need for additional corrective action.

If the corrective action is acceptable, follow-up action to verify implementation, documentation and close-out of the corrective action commitments is to be performed per approved procedures.

ENTERGY QA MANUAL OPERATIONS REV. 20 i \'n)

? OPERATIONS ARKANSAS NUCLEAR ONE SECTION:16.0 CORRECTIVE ACTION PAGE 16-1

. - = , -

16.2.4 3

(j g If agreement upon the resolution cannot be achieved, the condition is to be referred ta the appropriate level of management as specified in approved proculures.

16.3 SUPPLIER DEFICIENCIES When vendors furnish products or services that do not conform to the requirements of the applicable purchase contract and, in the opinion of Material Requirements, warrants additional evaluation, Material Requirements will evaluate the vendor's past performance using available information such as audits, receising inspection reports, industry notices, etc. Results of the evaluation will be used to determine the status of the vendor.

16.4 SIGNIFICANT CONDITIONS Significant conditions adverse to safety are to include, as a minimum, the following:

(1) Conditions that have a direct adverse effect on the safety of the plant per the plant Operating License and Technical Specifications (2) Conditions that have caused the uncontrolled release of radioactive materials (liquid, solid, gaseous or air particulate) to the emirons (3) Adverse quality trends which could lead to unsafe plant operations i

16.5 REPORTABLE EVENTS 16.5.1 When significant conditions adverse to safety are discovered, the Licensing Department is to evaluate the condition and determine ifit is an event reportable to the NRC. )

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16.5.2 Upon determination that a significant adverse condition is reportable, the Director, Nuclear Safety ensures that the appropriate report is initiated and subsequently transmitted to the NRC.

16.5.3 The PSC reviews Root Cause and Corrective Action plans for reportable events through its review of Licensee Event Reports (LERs).

16.5.4 The Licensing Department is responsible for transmitting approved reports to the NRC within the time period specified in the Technical Specifications and approved procedures.

-16.6 VERIFICATION Verification by sun eillance or audit of the effective implementation of corrective actions is to be periodically performed and documented by responsible Quality personnel. Audits are to be performed in accordance with Section 18.0 of this manual, n ENTERGY QA MANUAL OPERATIONS REV, 20 OPERATIONS (Vd ARKANSAS NUCLEAR ONE SECTION:16.0 CORRECTIVE ACTION PAGE 16-3

~. . _ ,. - .- -__ - -. - -

17.0 OUALITY ASSURANCE RECORDS s J 17.1 SCOPE

%d 17.1.1 ,

1 Documentation covering design, construction, procurement, fabrication, inspection, operation, maintenance, nonconformance and corrective action, test and audit activities is to be filed and stored to provide objective evidence of quality related activities and to assure the ability to reconstruct significant

" I events. Control of records is to be in accordance with Regulatory Guide 1.88, Rev. 2 (10/76) unless otherwise noted in Table 1.

1 17.1.2  :

Quality assurance records are to include operating logs; results of reviews, inspections, tests, maintenance, audits, material analyses; monitoring of work performance; qualification of personnel, procedures, and j equipment; historical drawings, specifications, personnel exposure, engineering reports, calculations, I i procurement documents, calibration procedures and reports, nonconformance reports, corrective action ]

, reports, correspondence and related records pertinent to quality as defined in approved procedures.  ;

l 17.2 RESPONSIBILITY 17.2.1 The Superintendent, Administrative Senices is responsible for the establishment, implementation and maintenance of the records management program to be used throughout the operational life of ANO and for ensuring that documentation retention requirements comply with applicable Technical Specifications, codes and regulations.

F ENTERGY QA MANUAL OPERATIONS REV. 20 OPERTIONS g) i ARKANSAS NUCLEAR ONE SECTION: 17.0 QUALITY ASSURANCE PAGE 17-1 V RECORDS I

l 17.2.2  ;

i p,

Personnel, other than plant staff, and outside firms who perform work on ANO in the areas of design, procurement, maintenance, modification, testing, quality assurance and special nuclear materials are to i provide documentation /cenification records to ANO for subsequent storage and retention by the Document Contr.,1 Center.

I 17.2.3 Quality Assurance personnel are to periodically audit quality-related records and records filing and storage procedures to assure that the records management program is being properly implemented. Audits are to be performed as outlined in Section 18.0 of tids manual.

17.3 DOCUMENTATION RETENTION 17.3.1' Lifetime Quality Assurance Records 17.3.1.1 f3 y8 Lifetime records are defined as those which meet one or n' ore of the following criteria:

(1) Those which would be of significant value in demonstrating capability for safe operation (2) Those which would be of significant value in maintaining, reworking, repairing, replacing or modifying the item (3) Those which would be of significant value in determining the cause of an accident or malfunction of an item (4) Those which provide required baseline data for insenice inspection 17.3.1.2 l Lifetime quality-related records are to be maintained for the life of the particular item while it is installed or stored for future use as prescribed in approved procedures.

l ENTERGY QA MANUAL OPERATIONS REV. 20 e OPERTIONS ARKANSAS NUCLEAR ONE SECTION: 17.0 QUALITY ASSURANCE PAGE 17-2 RECORDS i l

I

17.3.2 Non-Permanent Quality Assurance Records l ,I 17.3.2.1 u

Non-permanent records are defined as those which meet all of the following criteria:

(1) Those of no significant value in demonstrating capability for safe operation (2) Those of no significant value in maintaining, reworking, repairing, replacing or modifying the item (3) Those of no significant value in determining the cause of an accident or malfunction of an item (4) Those which do not provide baseline data for insenice inspection i 4

17.3.2.2 Non-permanent records are to provide evidence that an activity was performed in accordance with I applicable requirements and be retained for specified periods as directed by the approved procedures for document retention and disposition.

rs Q 17.3.3 Categories oflifetime and non-permanent records to be maintained and their appropriate retention periods are described in approved procedures.

17.3.4 Quality Assurance documents received from suppliers are inspected and approved as directed by approved procedures for procurement of mate:ial, equipment and senices.

l ENTERGY QA MANUAL OPERATIONS REV. 20 OPERTIONS

(' ARKANSAS NUCLEAR ONE SECTION: 17.0 QUALITY ASSURANCE RECORDS PAGE 17-3

I 17.4 STORAGE I

• 17.4.1 i

Lifetime records are to be stored within a controlled area per ANO approved procedures. This area must i 1

meet single storage requirements set by our commitments or must be replicated by microfilm, imaging, electronic files or other approved means according to site procedures. Duplication of these records is to be l made and duplicates to be stored at a remote location if they do not meet the requirements of single storage.

I 17.4.1.1 For storage of film and other special processed records, humidity and temperature controls are to be provided to maintain an emironment as recommended by the manufacturer and approved procedures.

17.4.1.2 A list is to be prepared in accordance with approved procedures designating those personnel who have access to the storage files.

7]3

! 17.4.2 Records storage systems are to provide for the accurate retrieval ofinformation without undue delay and be suflicient to control and account for records removed from the storage facility.

17.5 RECORDS INDEXING AND RECEIIT CONTROL 17.5.1 Indexing methods and systems for quality-related records are delineated in approved procedures for records management.

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERTIONS A)

(

ARKANSAS NUCLEAR ONE SECTION: 17.0 QUALITY ASSURANCE RECORDS PAGE 17-4

17.5.2 sm

(

.v

) Records submitted for storage in either lifetime or non-permanent files are to be subject to the following requirements for receipt control; (1) Establishment of a records list designating the required quality-related records (2) Establishment of a system designating criteria for document inspection to assure that records are complete, legible and received in good condition (3) A file system to indicate which quality-related documents have been received 17.5.2.1 Implementation of receipt control requirements for storage is the responsibility of the Superintendent,

' Administrative Services.

17.6 FINAL DISPOSITION The Superintendent, Administrative Senices is responsible for disposal of quality-related records in accordance with approved procedures for document retention and disposition, w hich permits periodic purging of records retained past their required retention date.

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18.0 AUDITS l'

18.1 SCOPE 18.1.1 A comprehensive system of planned and periodic audits is provided to ensure and verify comr 'iance with all aspects of the administrative controls and quality assurance program. Audits are ta be planned and performed in accordance with written procedures, plans and checklists and are to conform to the applicable portions of Regulatory Guides 1.144, Rev.1 (9/80), and 1.146, Rev. 0 (8/80), imless otherwise noted in Table 1.

18.1.2 The audit program is to include provisions to determine the compliance with and effectiveness of the QA Program in controlling structures, systems, components and activities in accordance with the rules set forth in the codes, standards and reguladons identified in the Introduction of this manual.

18.1.3 Where ANO is the supplier of senices to other Entergy Operations Incorporated (EOI) nuclear sites, Audits of these senices are conducted by Quality under the ANO Audit Program as described in this QAMO section.

O gj 18.1.4 Where ANO is the receiver of senices from other EOI sites, audits / assessments of the senices may be conducted by ANO or others(e.g. EOI QA groups, Nuclear Safety and Licensing or Assessment groups). These audits are subject to evaluation and approval by ANO Quality per Section 7.8.1 of this manual.

18.2 AUDIT PERSONNEL 18.2.1 l

The Supenisor(s), Quality Assurance and the offsite Manager, Material Requirements have assigned )

i auditing responsibility within the QA Program and are responsible for the selection and assignment of l

auditors. Auditors are to be independent of any din.-t responsibility for performance of the activity which is to be audited and are not to report to a management representative who has direct j responsibility for the activity being audited. l ENTERGY QA MANUAL OPERATIONS REV. 20 f OPERATIONS ,

ARKANSAS NUCLEAR ONE SECTION:18.0 AUDITS PAGE 18-1 II l

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l 18.2.2

') . . Auditors assigned auditing responsibilities are to have experience and training commensurate with the scope, complexity and/or special nature of the activities to be audited. When audit assignments are made, considerations are given to special abilities, specialized technical training, prior pertinent expertise, personal characteristics, education and capability. If no one within the Quality Organization meets these prerequisites completely, technical specialists are to be used to assist in the auditing of the j activity. Tec'mical specialists are to meet the requirements of paragraph 18.2.1 of this manual. I 18.2.3 Audit personnel are provided appropriate training to assure their competence for performing the required audits. Proficiency of audit personnel is maintained by one or more of the following methods: I (1) Regular, active participation in the audit process (2) Review and study of codes, standards, procedures and instructions (3) Participation in training or orientation programs 18.3 AUDIT SCHEDULE

(]

v 18.3.1 Audits are to be perfonned on a planned and periodic basis in accordance with an audit schedule. Audit schedules are to be prepared at the beginning of each year by the Quality Organization and approved by the Supervisor (s), Quality Assurance; Director, Nuclear Safety; and the SRC.

18.3.2 Audit schedules assure that the following areas are audited at least once every two years, or more frequently as performance dictates, under the cognizance of the SRC.

a. The confonnance of each unit's operation to provisions contained within the Technical Specifications and applicable license conditions.

b. The performance, training, and qualifications of the entire staff.

l n ENTERGY QA MANUAL OPERATIONS REV. 20

( OPERATIONS ARKANSAS NUCLEAR ONE SECTION:18.0 AUDITS PAGE 18-2

c. The r:sults of actions taken to correct deficiencies occurring in unit equipment, structure, I systems, or method of operation that affect nuclear safety, f)\

\

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix B.

e. The Offsite Dose Calculation Manual and Process Control Program and implementing procedures.

f. The radiological emironmental monitoring program and the results thereof.

g. The Headquarters QA Program

h. Any other area of unit operation considered appropriate by the SRC or the Vice

. President, Operations ANO.

I8.3.3 Audits of vendor / contractor activities are to be scheduled as identified in paragrapt 7.3.3 of this manual. These audits are to evaluate and verify their quality assurance program, proc edures and i

activities, to assure compliance with the procurement documents and to verify they rericdically resiew O

! and audit their suppliers' quality assurance programs. Audit schedules for vendor / contractor audits are U) approved by the offsite Manager, Material Requirements.

4 18.3.4 Periodic reviews of the audit programs are to be perfonned by the SRC oc their appointed management representative at least semiannually to assure that audits are being acco'.aplished in accordance with the requirements of the Technical Specifications, this manual and Regulatory Guide 1.33, Rev. 2 (2n8),

unless otherwise noted in Table 1.

18.3.5 3

Regularly scheduled audits may be supplemented, as required, to cover unforeseen events or changed requirements.

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4

l 18.4 .' AUD'IT IMPLEMENTATION

( '

-( 18.4.1  ;

Audit plans and checklists are to be prepared by the auditor and approved by the responsa,!c Quality l

management, or designee, prior to performing the audit. Checklists are to be used to ensure depth and continuity of audits in order to verify that those procedures and instructions issued to control the audited activity are adequate. -

1 18.4.2 Upon completion of an audit, a written report is to be prepared which includes at least the following items:

(1) Description of audit scope and date (2) Identification of the auditor (s)

(3) A summary of audit results (4) Details of nonconformances or programmatic deficiencies (5) Recommendations for correcting nonconformances or improving the QA Program, as O

t appropriate J

J i 18.4.3 Deficiencies identified as a result of an internal audit are to be recorded on a Condition Report (CR) by the auditor and issued to the Department Head responsible for the corrective action. The Department Head or the assigned designee is to provide prompt corrective action to the deficiencies identified and

for significant deficiencies, document on the CR the action taken or to be taken to preclude recurrence.

Appropriate follow-up including re-audits by the assigned audit group is conducted in the deficient

{

areas to verify proper and timely implementation of corrective action commitments. Follow-up actions are to be documented on the CR.

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ENTERGY QA MANUAL OPERATIONS REV. 20

() OPERATIONS ARKANSAS NUCLEAR ONE SECTION:18.0 AUDITS PAGE 18-4

1 1

1 l

18.4.4 j Intemal audit reports pertaining to plant operations activities are to be independently reviewed by the SRC to

. ' (" determine if additional corrective actions need to be initiated to assure continued safe operation of ANO.  !

Internal audit reports pertaining to other than plant operations activities are to be independently resiewed by the SRC. In addition to this review, the audit reports are to be distributed, as a minimum, to the Director, Nuclear Safety, Supervisor (s), Quality Assurance; and appropriate levels of management having responsibility l in the area audited to assure their awareness of the findings. )

l 18.4.5 1

1 Audit results and findings related to extemal audits conducted by Material Requirements personnel are to be recorded and distributed to ANO Records and to a designated representative of the audited organization as a minimum. Deficiencies r. e to be recorded and the audited organization is to describe actions taken to correct deficiencies and prevent recurrence. Corrective actions are to be verified by Material Requirements personnel and documented.

I 18.5 RECORDS )

1 Written intemal/extemal audit reports, including checklists, CRs, vendor / contractor findings, and related j q documentation supporting the follow-up activities are to be forwarded to the Document Control Center for I b storage in accordance with Section 17.0 of this manual. I 18.6 NUCLEARFUEL AUDITS  ;

The offsite Manager, Material Requirements has the responsibility for performing those quality assurance i functions necessary to assure that its nuclear fuel is designed and fabricated in accordance with regulatory  !

requirements and accepted codes, standards and specifications. Material Requirements monitors the design and fabrication of the fuel through a program of audits of the fuel fabricator, including both design resiew audits and fuel fabrication audits. Material Requirements also conducts audits of component suppliers as l

deemed necessary to assure the quality of the fuel and issues formal audit reports to document audit actisities l l

and to identify nonconformances or other items requiring action by the fuel fabricator. Resolution of -

nonconformances or other items requiring action is verified by Material Requirements and documented in follow-up reports. These audit reports are to be forwarded to ANO Records and stored in accordance with Section 17.0 of this manual.

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ENTERGY QA MANUAL OPERATIONS REV. 20 in) OPERATIONS ARKANSAS NUCLEAR ONE SECTION:18.0 AUDITS PAGE 18-5 l

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-18.7 HEADQUARTERS QA PROGRAM AUDI7 c.,

The offsite Vice President, Operations Support has the responsibility for planned and periodic internal audits of the Headquarters QA program for those activities performed to, support and satisfy the

! requirements of the ANO QA program.

t The onsite Director, Nuclear Safety has the responsibility for performing periodic audits of the Headquarters QA program to assure that this program continues to satisfy ANO QA Program r requirements delegated to Headquarters.

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) OPERATIONS ARKANSAS NUCLEAR ONE SECTION:18.0 AUDITS PAGE 18-6

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CORPORATE ORGANIZATlONS ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: FIGURES PAGE F-1

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VICE PRESIDENT __3 __

y OPERATIONS ANO I

1 GENERAL MANAGER, 1 PLANT OPERATIONS I

t l l PLANT M ANAGER PLANT MANAGER U NIT-1 U NIT-2 l l

l SEE FIGURE F-3 l l SEE FIGURE F-4 l l I

MANAGER  ! MANAGER MANAGER IN OPS MANAGER RADIATION OUTAGE AND CERTIFICATION STANDARDS PROTECTIONI WORK TRAINING CHEMISTRY l MANAGEMENT c____J W THE MANAGER. RADIATION PROTECTION REPORTS TO MANAGER THE MANAGER. RADIATION PROTECTION / CHEMISTRY IN ADMINISTRATIVE MATTERS AND ROUTINE RADIATION RADIATION PROTECTION AND RADWASTE CONCERNS AND TO THE PROTECTION VICE PRESIDENT. OPERATIONS ANO IN MATTERS OF RADIOLOGICAL HEALTH SAFETY AND POLICY. 'i PLANT OPERATIONS DEPARTMENT ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: FIGURES PAGE F-2

. _. . .__ . . . _ . _ . . - . . . . . . _ . . _ _ _ . . . - . . . ~ . . . . . _ . . _ _ _ . . . . . . . - . _ , . . . . . _ . . . . . _ m.. . . . . . . ..

i 1 ( ')

V t

i PLANT MANAGER UNIT-1 l l

I I ,

MANAGER MANAGER

^^ MANAGER SYSTEM OPERATIONS MANAGER MAINTENANCE STANDARDS ENGINEERING e OUTAGES 4

i L

NRC SEMOR REACTOR OPERATORS UCENSE REQUWtED

" ACTIVE NRC SEMOR REACTOR OPERATORS UCENSE ASS STA TS TO  !

REQUWtED SHIFT PLANT MANAGER OPERATIONS

"" ACTIVE NRC REACTOR OPERATORS UCENSE REQUWtED e.

i i

CONTROL SHIFT ROOM ENGINEERS I SUPERVISORS e.

I i

CONTROL WASTE I AUXILIARY BOARD CONTROL OPERATORS OPERATORS OPERATORS e.e J

(9 The prefect manegere. outages unit 1 and 2 esport to the manager owege and wert menesesneen k adowstrative i saatters and to the Plant M apogers Unit t & 2 e  :, en mattere related to specific plant eutege activillee, i

UNIT 1 OPERATIONS ORGANIZATION l

ENTERGY QA MANUAL OPERATIONS REV. 20 i OPERATIONS t ARKANSAS NUCLEAR ONE SECTION: FIGURES PAGE F-3

" _ ._ ... . . _ . . . . _ _ . .~ _ _ _ ,,, . . . _ _

Q/ (q [j'\'

PLANT MANAGER _ _ _ _

UNIT-2 l I

I f

l I l

MANAGER MANAGER MANAGER PROJECT TECHNICAL

• l SYSTEM MAINTENANC OPERATIONS MANAGER ASSISTANT TO ENGINEERING E .

OUTAGES PLANT MANAGER l

l

' NRC SENIOR REACTOR OPERATORS LICENSE REQUIRED l SUPERINTENDENTS

" ACTNE NRC SENIOR REACTOR OPERATORS LICENSE f REQULRED SHIFT l OPERATIONS

"* ACTfvE NRC REACTOP OPERATORS LICENSE REQUIRED ..

I CONTROL SHIFT l

l SUP RVI ORS l

- -m ,

CONTROL WASTE AUXILIARY BOARD CONTROL OPERATORS OPERATORS OPERATORS

,,,_.__..._0_.._...._,....O_........._._. . . . . . . . . _ . . . . _ . . - . .

UNIT 2 OPERATIONS ORGANIZATION .

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: FIGURES PAGE F-4 L

O O O DIRECTOR 2 NUCLEAR SAFETY ,

I  :

MANAGER NUCLEAR SAFETY I _

l l l l i SUPERVISOR SUPERVISOR SUPERVISOR IN OUSE ES UCENSM - UCENSM - INDUSTRmEMS ANALYSIS & REG M ANAWSIS RR ASSESSMENT ,

, s k

b k

f LICENSING DEPARTMENT ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS  :'

ARKANSAS NUCLEAR ONE SECTION: FIGURES PAGE F-5 i

i

O O O SLPPORT l l I exCa wnmeR REVIEW OFFICERI SITE BUSINESS SUPPORT PWSICM SUMCES SPECIE SUPERMDMT SUPSWHDMT P M ECTS ao-SmAMVE PUWT SUMCES SECUm Y i

SUPPORT DEPARTNENT i

l ENTERGY QA MANUAL OPERATIONS REV. 20 l r OPERATIONS '

ARKANSAS NUCLEAR ONE SECTION: FIGURES PAGE F-6 1

' /' % m ,

N V- t DIRECTOR

• NUCLEAR SAFETY COORDINATOR ,

QUALITY i

I I SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR QUALITY QUALITY QUALITY NDE ASSURANCE ASSURANCE CONTROL i

QUALITY DEPARTMENT i

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: FIGURES PAGE F-7

._.__.___._.____._m.-. -

. _ _ _ . . _ _ _ _ _ _ _ . . _________.__m__.____.__.__ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ _

(v)

• This tctisity his beem deleg ted to 3

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9 A

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Ct O

M s

O C

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N 5 N R C ; Q O A A

IJ 9

Ifendquarters, QA A P I C T tr T N T T T T S P C R R R N R c U R M T E R O E r T program and I O N R E O O C C O s T N C C s procedures which Z C E P N F 0 F T O L T E P T O T A nu r 1 A R C St R T F I N O O I g3ggg4 S R are periodically T A O E O S O T O E T R V D audited by ANO' ' " " " C C ' C " " " ' ^ " ' '

O T T O t1 O E O G A I N R A N R N C L M E N A l l

• * ' ' "C QUALITY ASSURANCE C D

R O A O P

R IE

& ?

E I I

^ ' "

PROCEDURES MATRIX C O I D

E I

5 M N N I 5 P T S Y C I T 5 A R S T E E T O E M S tf L M S 5 5

Q OlO PIUt'RFS ORGANIZATION ('ILtRTS X OP-1000 001 ORG ANIZATION AND RESPONStBI!JTY X QAD-1 NtTLF AR Qt'AIJTY ORG4Nt7ATION X QtD-2 , L%IMMTRLNATION A TRAINING OF QL'AIJTY PFRSONNP L X OP-l#00.OlF _51 ATION TRAINING PRIM;R.01 X Q 4 D-3 DISTRIRtTION OF CONT RotJ.ED NQ IMM'l3fENTS X X QAD6 INTFRN AL At'DITS X X OP 8000.103 PIANT MODIFICATION PROCFSS X OP-1000153 FNGINFI. RING RP Qt TST PRotTSS X OP4010 001 DCP DF4 FLOPMFNT X OP-1000 012 CONTRACT ADMINISTRATION X X OP$010006 DESIGN FNGINEP RING PREM'I'RFMENT RFQtTSTS X OP.1033 005 CON 1ROL & USE OF MATERIA 1/RFQtTSTS PROCFDL'RE CONTROL X OP-3 000 006 PROCFDi'RE C1 .% DL X X OP-6610100 DRAWING PREP LTION AND RF4TSION X OP-5010 e04 DESIGN IMMTMENT l'PDATFS X Q4D-3 PREPARATION AND ISStY OF NQ IMM't31ENTS X OP-1033.001 RFCFIPT INSPFiTION X

• X

\TNIN)R QUAIIFICATION PROGRAM

• \TNDOR SCR\TIIJ.ANCE X OP-1033.002 ('ONTRot. EDF MATFRL4L X X OP-5000.009 WELDl%G PROGRAM ADMINISTRATION X OP-5000.009 Rf PAIR /RFPLACEMENT PROGR.Of ADMINISTRAl' ION X QCO-7 NDE (VT) FX AMINATION X QC46 WFl_ DING INSPFCTION X QC43 MAINTEN ANCE & MODIFICATION QC INSPFCTION X OP-1006 009 StltVFII. LANCE TEST CONTROL X OP-IO92.026 ISI PROGRAM RFQt'IRFMENTS X OP-1000.014 CONTROL OF MATE STAND ARDS X OP-1000.024 ('ONT ROL OF M41NTEN ANCE X OP-IOce.027 IlOLD AND CALTION CARD CONTROL X OP-IOOO.029 TEMPOR ARY MotMilCAT10N ('ONTROL X OP-1000.3 04 CONDITION REPORTING AND CORRFCT1VE AC110NS X X Q4D-RO CORRECT 1\T ACTION X OP-IOl3 082 IMM 13 TENT CONTROL PROCFDt'RE RFQt'IREMENTS X OP-1913 005 RFCFIPT AND PROCESSING OF RFCORDS X

• \TNDOR/ CONTRACTOR Al DITS X OP-1983 006 MICROGRAPIIICS X ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE 2 PAGE T2-1

.. . _ . . . _ _ .. . . _ . . _ _ . . . _ . _ ~ _ . _ _ . . _ . _ _ _~ _ . . _ . _ _ . _ .

TABLE 3 4

4 , , QUAUTY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION

" J/ MANUALS UST k

i-e

l. Quality Assurance Manual Operations

j. The Quality Assurac e Manual Operations establishes the policies and guidelines of the QA Program l for ANO. This program is to be followed by all organizations involved in safety-related work applicable to ANO.

i 5

2. Overall Administrative Procedures 4

4 r j- The Nuclear Organization employs a system of procedures designated as Overall Administrative Procedures (OP-1000.XXX, OP 5000.XXX or OP-6000.XXX series). Rese procedures implement

'the QA Program requirements and control safety-related activities. Overall Administrative Procedures j- and changes thereto are prepared by the responsible department, reviewed by the Plant Safety j Committee and approved by the Major Department Head. He procedures and revisions are also reviewed by a Supervisor, Quality Assurance to assure that the QA Program commitments are met.

Review and approval of Quality administrative procedures is described in paragraph 5 below.

I.O i

LJ l'

3. Departmental Procedures s

Each department (excluding Quality) within the Nuclear Organization has developed procedures in support of the Overall Administrative Procedures and the QA Program. %ese procedures provide technical and administrative instructions to the respective departments to aid in implementing their

. responsibilities within the QA Program. Each Department Head is responsible to perform a review of )

i. their procedures to assure conformance with the QA Program.

I i

1 Procedures required by the Technical Specifications are reviewed and approved as described in l paragraph 5.3.2 of this manual. I 4

5

g. ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS l ARKANSAS NUCLEAR ONE SECTION

TABLE 3 PAGE T3-1 j .-

4

, . . . - ~ --

. . _ ~ .-. . -_ ~ - - . . .

4. Headquarters Procedures

-Q The Nuclear Organiation employs headquarters procedures that may control safety related activities conducted at ANO. Rese procedures and changes thereto are reviewed by the Plant Safety Committee and approved by the responsible Major Department Heads. He Major Department Heads assure l

conformance of these procedures with the QA Program.

I The Materials Requirements organiation employs a system of procedures developed to assure implementation of their responsibilities within the QA Program. Materials Requirements management assures conformance with the QA Program.

5. Quality Procedures The Quality Organintion employs a system of procedures developed to assure proper implementation of the QA Program. Rese procedures provide technical and administrative inttructions to the Quality staff to aid in implementing their responsibilities within the QA Program. Rese procedures are j reviewed / approved by a Supervisor, Quality Assurance, Supervisor, Quality Control, or Supervisor, NDE and the Director, Nuclear Safety.

He Materials Requirements organiation employs a system of procedures developed to assure implementation of their responsibilities within the QA Program- Materials Requirements management assures confonnance with the QA Program.

g ENTERGY QA MANUAL OPERATIONS REV. 20 i OPERATIONS

'- ARKANSAS NUCLEAR ONE SECTION: TABLE 3 PAGE T3-2

DIRECTOR QUALITY 4

COORDINATOR QUALITY SUPERVISOR SUPERVISOR SUPERVISOR

, SUPERVISOR QUALITY QUALITY QUALITY NDE ASSURANCE ASSURANCE CONTROL QUALITY DEPARTMENT ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: FIGURES PAGE F-7 L e o e

TABLE 1

/~N (g ARKANS AS NUCLEAR ONE EXCEPTIONS / INTERPRETATIONS OF REGULATORY GUIDES AND ANSI STANDARDS APPLICABLE TO THE QA PROGRAM Regulatory Guide / Exceptions /

ANSI Standard Reauirement Interpretation General Certain Regulatory The ANO commitment refers Guides invoke or to the Regulatory Guides and imply Regulatory ANSI Standards, specifically Guides and standards identified in this manual. I in addition to the Additional Regulatory Guides, standard each ANSI Standards, Guides and primarily endorses. similar documents implied Certain ANSI Stan- or referenced in those dards invoke or specifically identified in imply additional this manual are not part of

( standards. this commitment.

General Certain ANSI Our commitment to those Standards and/or standards applies only to Regulatory Guides those systems, structures, extend the scope of and components whose satis-applicability to factory performance is include systems, required to prevent postu-structures, and lated accidents that could j components whose cause undue risk to the  !

satisfactory perfor- health and safety of the mance is required public; or to mitigate for a plant to the consequences of such operate reliably on accidents. Reliable operation ENTERGY QA MANUAL OPERATIONS REV, 20 p j OPERATIONS I ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE TI-I i

i

"high-value of the plant may depend upon articles." other systems, structures and

/~'s components which are not coverxi by this commitment.

ANSI N18.7 The following ANO has committed to R.G.1.58, (Section 5.2.7) standards contain Rev.1/ ANSI N45.2.6 - 1978

..during initial winch shall be used in lieu of plant design and 1973 edition.

construction. AWS Qualification of Inspection, Exandnation and Testing Personnel i for the l Construction Phase of Nuclear Power Plants, N45.2.6-1973..

l g r'\ i (j ANSI N18.7 The causes of the ANO will comply with this

]

(Section 5.2.7.1) malfunctions shall requirement, where applicable.

be promptly This clarification is needed determined, since it is not always possible evaluated, and to promptly determine the recorded. cause of the malfunction.

ANSI N18.7 Where changes are Consistent with the require-(Section 5.2.13.1) made to procure- ments of ANSI N45.2.11, para-ments, they shall graph 7.2, minor changes to be subject to the (procurement) documents, such same degree of as, inconsequential editorial control as was used corrections, or changes to in the preparation commercial terms and conditions

,- ENTERGY QA MANUAL OPERATIONS REV. 20 t OPERATIONS

\ ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE TI-2

of the original may not require that the re-documents. vised (procurement) document

! receive the same review and j

l approval as the original documents.

l l

\

ANSI N18.7 Plant procedures Programmatic controls that are l (Section 5.2.15) shall be reviewed equivalent to or better than by an individual the biennial review process knowledgeable in have been implemented at ANO.

the area affected These programmatic controls by the procedure are effected in an effort to I no less frequently ensure that procedures are than every two reviewed for possible revision years to determine upon identification of new or if changes are revised source material necessary or potentially affecting the desirable. content of procedures, thereby maintaining the procedures A

( current. Entergy Operations believes that this approach better addresses the intent of ANSI N18.7-1976 and is more acceptable from both a technical and practical perspective than a static two-year review process.

p ENTERGY QA MANUAL OPERATIONS REV. 20

('j OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE TI-3

ANSI M18.7 Records shall be Not allinspections will j

, (Section 5.2.17) kept in sufIicient require generation of a detail to permit separate inspection report.

adequate confir- Inspection requirements may mation of the in- be integrated into appro-spection program, priate procedures or other documents with the procedure or document sening as the record. However, records of inspections will be identi-fiable and retrievable.

Reg. Guide 1.33 Establishes minimum 2 year Audits of safety-related functions (Section 4) audit frequency for all will be performed at frequencies safety-related functions and based on analysis of performance recommends audit frequencies indicators, with a two year maximum specific to Corrective Action, duration between audits of any specific Facility Operations, and area.

Staff Performance, Training (D

g and Qualifications.

ANSI N45.2.1 Fresh water criteria The turbidity requirement on (Section 3.2) for chlorides, and fresh wateris deleted and Jackson Turbidity the chloride requirement is Units, revised to read "less than 250 ppm." The turbidity requirement for demineralized water is deleted.

ANSI N45.2.2 Preliminary sisual Inspection after unloading is Subsection 5.2.1 inspection or exami- sufficient to determine the nation shall be per- condition of many items. In formed prior to special instances. pre-unload-unloading.. ing examination is performed.

es ENTERGY QA MANUAL OPERATIONS REV. 20 I ) OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE I PAGE TI-4

l ANSI N45.2.2 The (receiving) Receiving inspection is per-l Section 5.2.2 inspections shall formed in a manner and in an

.(x) be performed in an emironment which does not area equivalent to endanger the requisite quality the level of storage of an item. The receising requirement for the inspection area emironmental item. controls may be less stringent than storage emironmental requirements for that item; however, the short time spent in the less stringent receiv-ing inspection area shall be  !

of such duration that will not adversely affect theitem being received.

ANSI N45.2.2 ..The 'Special The "SpecialInspection" Paragraph 5.2.3 Inspection' pro- procedure shall be readily cedure, complete available to inspection

.Q with documentation personnel and may be attached l

l.

instructicas shall to the item or container. ,

i be attached to the ,

l item or container..  !

I i

ANSI N45.2.2 The use or storage People working in storage )

l Subsection 6.2A of food, drinks, and areas have a right of access  !

salt dispensers in to water dispensers per OSHA I any storage area is requirements. Additionally, I prohibited. due to the location and layout of the building, per-

! sonnel may temporarily store lunches in the work place.

This area is policed for sanitation.

- ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE I PAGE TI-5 .

1 i

l

4.

ANSI N45.2.2 Ccre cfitems in Types of components that (Section 6.4.2) storage shall be could require maintenance 4

p' g exercised in while in storage shall be accordance with identified and evaluated g the following: for specific maintenance requirements. Maintenance

activities 6.4.2(6) through (8) listed in this requirement shall be considered during this evaluation and any deviations shallbe

'. justified and documented.

4 ANSI N45.2.2 Container markings Containers are adequately a

Appendix (A-3) shall appear on a marked for storage, identifi-1 A.3.9 (1) Second mini. mum of two sides cation, and retrieval.

Group of the container, Multiple marking requirements preferably on one are imposed, where necessary.

side and one end.

f% \

\

v' ANSI N45.2.2 Container markings Container markings are of a Appendix (A-3) shall be...no less size which permits easy A.3.9 (4) Second than 3/4" high, recognition.

Group container permitting.

ANSI N45.2.2 Container marking The information required Appendix (A-3) shallinclude the in container marking is A.3.9 following informa- cvaluated on a case-by-tion.. basebasis. Markingis adequate in each case.

ANSI N45.2.2 Non-metallic plugs Non-metal p,ogs and caps are Appendix (A-3) and caps shall be of a suitably visible color.

Section A 3.5.1 (1) brightly colored.

= =.=.

g ENTERGY QA MANUAL. OPERATIOhd REV. 20 Qg OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE I PAGE TI-6

ANSI N45.2.2 Plugs or caps shall in cases where plugs or caps

.y I Appendix (A-3) be secured with tape do not snugly fit, additional l

Q Section A 3.5.1 (5) or other means as securing devices or measures necessary to prem which will not be detrimen'.al accidental removal. to the item will be used.

j ANSI N45.2.2 Marking ofitems The last paragraph of Section Appendix (A-3) not within a con- A.3.9 could be interpreted as Section A 3.9 . tainer. prohibiting any direct marking

]

on bare austenitic-stainless- j 1

steel and nickel-alloy metal l l

surfaces. In lieu thereof, j

. gragraphs A.3.9. (1) and (2) l will be used to control

. marking on the surface of l austenitic-stainless-steels j and nickel-base alloys subject l to the following limitations:

" Marking materials containing

]

V. sulfur, lead, zinc, mercury, i 1

s copper and low melting alloys i

as a basic chemical consti-tuent shall not be brought in contact, or shall not be used on surfaces of corrosion-resistant alloys. Low-sulfur,

low fluorine and/or low-chlorine compounds may be used on austenitic stainless steels." The maximum limits for the above mentioned mark-ing materials will be as j follows

, ENTERGY QA MANUAL OPERATIONS REV. 20

\g OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE I PAGE TI-7

.~ - ~._ ._- .~... -. - -_ . . - . ~ . _ . . . . . . . - . -.. . - - . . . . -=

(a) Totalinorganic and organic halogen content i ' f)

= _ (y shall not exceed one (1)

. percent.

(b) The sulfur content shall not exceed one (1) percent.

ANSI N45.2.2 Inert Gas Blankets There may be cases involving large or complex shaped items for which an inert or dry air purge is provided, rather than a static gas blanket, in order to provide adequate protection due to difficulty of providing a leak proof barrier. In these cases, a positive pressure purge flow I

may be utilized as an alter-nate to a leak-proof barrier.

ANSI N45.2.2 Limits halogen and Engineering may allow the use

$ Appendix A, sulphur content of of tapes containing greater A3.5.2, (1), (a) tape. amounts of halogens after appropriate evaluation;

{.

. however, the quantities shall

! not be such that harmful concentrations could be leached or released by break-down of the compounds under expected emironmental conditions.

ENTERGY QA MANUAL OPERATIONS REV. 20

( OPERATIONS

\

ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE TI-8

Regulitory Guide . General Alternative equivalent

_ _ l.39 ANSI N45.2.3 requirements may be utilized l to cover those situations not

.~

i included in the subject Standard; for example, situa-l tions in which shoe covers l

and/or coveralls are required j but material accountability j

, is not. In addition, zones might be combined into the next more restrictive category in order to reduce total number of zones.

l ANSI N45.2.3 Identifies various When this standardis applied, I housekeeping re- its requirements are imple- I quirements, includ- mented in those areas affected ing cleanliness, by work activities associated f.re prevention, with modifications, opera-

! and fire protection tions, or maintenance as which must be determined necessary by plant accomplished during staff. l the progress of 1

I ConstmClion.

i Regulatory Guide Pre-Construction / 1 s section required verifi-1.30/ ANSI N45.2.4 Installation Verifi- cation that items are in l cation satisfactory condition for Regulatory Guide installation and have not 1.116/ ANSI N45.2.8 suffered since initial receiptinspection. Upon receipt, items are inspected and stored in an enviromnent which will not adversely n ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS l ARKANSAS NUCLE /.R ONE SECTION: TABLE 1 PAGE TI-9 ]

., ,. - - .-.. ._ . - - . .. _ - . - . ~ . . - .. _- . . - _

affect the item. Documented

,m routine inspections and i l Q periodic audits of the storage j

! areas assure that stored items are maintained in satisfactory

, conditions. Documentation of pre-construction verifica-tion in addition to documen-tation ofinitial receipt inspection, periodic storage 1

instsections, and audits of . j r storage is not required.

ANSI N45.2.4 Identifies various These tests will be performed j tests to be as determined by Engineering i

performed. or Nuclear Operations based '

upon the significance of change or modification.

1 l

i

. Q, R.G.1.58 In addition... the ANO takes exception to this j (Section C.6) candidate should be requirement. ANO's education a high school and experience requirements graduate or have are in accordance with ANSI  ;

earned the General N45.2.6-1978. I Education Development ]

(GED) equivalent of i a high school diploma.

j k.G.1.74/ Definitions of Based upon the guidance of ANSI N45.2.10 Certificate of ANSI N45.2.13,10.2, the Conformance and definitions of these two Certificate of terms will be exchanged.

Compliance.

p ENTERGY QA MANUAL OPERATIONS REV. 20 i/ OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE T1-10 l

I

R.G.1.94/ Section 1.4 defines This requirement for rein-ANSI N45.2.5 inprocess tests and forcing steel will be (Section 1.4) states: interpreted to permit taking the rebar test specimen at

" .. samples of these the fabrication shop, prior tests must be taken to start of fabrication of from the lot or the rebar from the heat or batch of materials fraction thereof represented supplied to the site by the test specimen. For .

for use." those tests perfonned at the 1 fabrication shop, certifica-tion shall be available to l provide objective evidence l 1

that the test specimens l represent the material sup- I plied for use at the site. I ANSI N45.2.5 Requirement:

(Section 4.5) Section 4.5 Con-

]

(J) crete Placement, references American Concrete Institute l (ACI) Standards ACI-305-72,

" Recommended Prac-tice for Hot Weather Concreting" and ACI-306-66, " Recommended Practice for Cold Weather Concreung."

]

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE I PAGE T1-11

. .. . . -. -_ -- ._ ._ - . . - . _=.-- - .

Interpretation:

l In order to clarify use of these ACI standards, we will l i-apply the following requirements:

)

l PLACING TEMPERATURES OF CONCRETE:

A. During hot weather concreting:

Placing temperatures of concrete will be limited to the following:

1) Concrete members less than 3 feet in least dimension will not exceed 90 F.

l

2) Concrete members from 3 feet to 6 feet in least dimension will not exceed 70 F.

(Oj 3) Concrete members more than 6 feet in least dimension will have placing temperature as near 50*F as can be obtained by use ofice as necessary up to 100 percent of adding mixing water, and by shading aggregate and sprinkling the coarse aggregate the day it is to be used. Care will be taken so that no unmelted ice remains in the concrete at the end of the mixing period.

B. During cold weather concreting:

In heating the water and aggregate, live steam to heat the fine and coarse aggregate shall not be used. The permissible range for concrete ,

temperature shall be as follows:

l L

i p ENTERGY QA MANUAL OPERATIONS REV. 20

( OPERATIONS j ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE T1-12 l i

1 I

1) Sections less than 3 feet in least dimensions: 55 to 75'F '

in 1 2). Mass concrete 3 feet or more in least dimension: 45 to 65 F >

The mixing water and aggregate will be purchased as required. The  !

materials will be free ofice, snow and frozen lumps before they enter the ,

mixer.

ANSI N45.2.5 Requirement:

(Section 4.8)

Section 4.8, "In-process Test on Concrete and Reinforcing Steel" states,

" Samples for in-process test of concrete shall be taken at the sampling point in accordance with ASTM C172. This point may be at the truck mixer discharge if the last piece of conveying equipment is a chute, bucket, conveying system, or similar equipment. Pump concrete must be sampled from the pump line discharge."

Interpretation:

r%

For performance of correlation tests, the requirements of ANSI N45.2.5-1974 shall be followed.

ANSI N45.2.5 Requirement:

(Section 4.8)

Section 4.8, "In-process Tests on Concrete and Reinforcing Steel" contains Table B entitled, " Required in-process Tests." The following modifications to  ;

this table will be applied:

1 Interpretation: I l

REINFORCING STEEL i l

In-process testing of reinforcing steel will include the mechanical properties of I

I' yield strength, tensile strength and percent elongation on full size specimens l'

F

. - . ENTERGY QA MANUAL OPERATIONS REV. 20

. OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE I PAGE T113 I

t 0

j for each bar size for each 50 tons or fraction thereof from each mill heat. Bend tests are performed during material qualification testing only, except as noted

.O i'Q below for bar sizes #14 through #18.

J Table A. " Required Qualification Tests" as applied to reinforcing steel will include bend tests as required by ASTM A615 and summarized below;

a) For bar sizes #3 through #11, one full size specimen from largest bar size rolled from each mill heat, unless material from one heat differs by three

~

or more designation numbers. When this occurs, one bend test shall be I

made from both the highest and lowest designation number of the deformed bars rolled.

1.

b) For bar sizes #14 through #18, Supplementary Requirements Sl of f' ASTM A615 will be applied, i.e., one full-size specimen for each bar size for each mill heat. If supplementary requirements are not followed for mill tests, they will be applied as in-process tests.

The above interpretation is consistent with Regulatory Guide 1.15, " Testing i Reinforcing bars for Category 1 Concrete Stmetures," Revision 1, December ,

1972.

i l

I In-process test specimens may be selected at the rebar fabrication shop, prior to i'

start of fabrication of the rebar from the heat or fraction thereof represented by the test specimen.

Acceptance criteria for any failed test (qualifications as well as in-process) may be the same as that for tensile tests specified in Subarticle CC-2331,2 of ASME Section III Div. 2 Code (1975). This states that if a test specimen fails to meet the specified strength requirements, two (2) additional specimens from the same heat and of the same bar size would be tested, and if either of the two additional specimens fails to meet the specified strength requirements, the material represented by the tests would be rejected for the specified use.

ENTERGY QA MANUAL OPERATIONS REV. 20 OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE T1-14 1

Alternative use of rejected material under strict control may be subject to evaluation by the Project Engineer.

ANSI N45.2.5 Requirement:

(Section 4.9)

Section 4.9 Mechanical (Cadweld) Splice Testing states in paragraph 4.9.4

" Separate test cycles shall be established for mechanical splices in horizontal, vertical and diagonal bars, for each bar size and for each splicing crew., "

Interpretation:

The terms " horizontal, vertical and diagonal bars" will be interpreted to apply respectively to the following types of splice positions:

a. Horizontal, including 10* to horizontal

b. Vertical, including 10* to vertical

c. 45* angle, including 10* to 80* angle The words " splicing crew" will be interpreted to refer to all members on the Q project that are actively engaged in preparing and assembling Cadweld mechanical splices at the final splice location. Separate test cycles will be established for each bar size and each splice position.

ANSI N45.2.9 As a minimum, a When records are submitted (Section 4.3) receipt control for storage, personnel system shall receiving the records are include procedures not subject to the for receipt and requirements of ANSI N45.2.6-inspection of 1978 nor Section 10.0 of this incoming records. Manual for inspection of incoming records.

ANSI N45.2.12 An individual audit For those routine audits (Section 4.2.1) plan describing conducted during operations, e ENTERGY QA MANUAL OPERATIONS REV. 20

$ OPERATIONS ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE T1-15

l the audit to be a written procedure (s) performed shall be covering each audit may be D

Q developed and utilized. Procedure (s) will documented by the identify the audit scope, auditing organiza- a requirement that individual tion. This plan checklists be utilized list- ,

1 shallidentify the ing requirements which are to audit scope, the be audited and notification requirements, the of the audited group.

activities to be audited, organiza-tions to be notified, the applicable documents, the schedule, and written procedures or check-lists.

ANSI N45.2.12 Management ...shall In concert with Appendix B, O

gg (Section 4.5.1) resiew and investigate Criterion XVI(Corrective any adverse audit Action) and Section 16.0 findings to determine of this manual, only and schedule appropriate those audit findings corrective action to classified as significant j including action to under the site corrective l l

prevent recurrence.. action system will require The response shall recurrence control and j clearly state the action within thirty days; corrective action taken non-significant findings )

I or planned to prevent will be resolved in a recurrence. In the event timely fashion consistent that corrective action with site corrective l cannot be completed action system requirements. j within thirty days, the l j

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ARKANSAS NUCLEAR ONE SECTION: TABLE 1 PAGE TI-16 i

-- - .. . =- . .. .. -_ . . - - -

audited organization's

- response shallinclude a scheduled date for the corrective action.

ANSI N45.2.12 Followup by auditing The followup actions (Section 4.5.2) organization. Followup prescribed in this action can be paragraph will be accomplished through administered through the

..other appropriate procedural requirements means. of the site Corrective Action System.

Corrective action plan resiew will only be performed for significant audit findings.

ANSI N45.2.13 The certificate The person attesting to a (Section 10.2.d) should be attested certificate shall be an to by a person who authorized and responsible is responsible for employee of the supplier, this quality assur- and shallbe identified by ance function and the Supplier.

whose function and position are described in the Purchasefs/

Suppliefs quality assurance program.

R.G.1.64 (Section While design Consistent with the require-

C.2)/ ANSI N45.2.11 verification by the ment of ANSI N45.2.11, I designefs immediate paragraph 6.1, design verifi-supenisor is en- cation may be performed by REV. 20 p)

ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE QA MANUAL OPERATIONS SECTION: TABLE 1 PAGE T1-17

couraged,it should the originator's supenisor, not be construed if the supenisoris the only A

that such verifi- individualin the organization cation constitutes competent to perform the the required inde- verification.

I pendent design verification, ANSI N45.2.23 Certification of ANO considers holders of NRC-l (Section 2.3.1.3) competence in issued Reactor Operator /

engineering, Senior Reactor Operator ,

1 sciences, or License to comply with the  ;

quality assurance requirements of the section a 1 1 specialties issued and may award two (2) credits ,

l and approved by a to those individuals. l

,. State Agency, or j National Professional l or Technical Society, i 1

score two (2) credits.

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Reg. Guide 1.88 The Requirements and ANO is committed to meeting the (Section C)/ ANSI N45.2.9 Guidelines for collection, requirements of ANSI /ASME NQA-1-1983 storage and maintenance Supplement 175-1, Section 4.4 in lieu of l

of Nuclear Power Plant N45.2.9-1974, Section 5.6 for record storage

, Quality Assurance Records facilities.

that are included in ANSI N45.2.9-1974 are acceptable 3

to the NRC staff and prosides

an adequate basis .

t ENTERGY REV. 20 q QA MANUAL OPERATIONS

, Q t OPERATIONS ARKANSAS NUCI. EAR ONE SECTION: TA.BLE 1 PAGE T1-18 4

APPENDIX A t'

QUALITY PROGRAM FOR TRANSPORT PACKAGES

1.0 INTRODUCTION

1.1 The quality program for transport packages containing radioactive material is designed to comply with the requirements of this manual and with the quality assurance guidelines identified in 10CFR71, Subpan H - Quality Assurance, subject to exceptions noted in Attachment A to this Appendix.

1.2 Attachment A to this Appendix identifies the applicability of each section of the Quality Assurance Manual Operations to the Quality Program for Transport Packages.

i 1.3 Attachment B to this Appendix contains the Quality Assurance Program Approval document which shows NRC approval of this program on January 18,1995.

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t OPERATIONS ARKANSAS NUCLEAR ONE SECTION: APPENDIX A-QUALITY PAGE AA-1 PROGRAM TRANSPORT PACKAGES

I ATTACHMENT A 10CFR71 Appendix H i

l The following sections of the most currently approved revision of the QA Manual Operations will be applied -

as stated below (Note specific paragraphs are to ievidan 10 paragraph numbers which could change during subsequent revisions).

Section 1 - Applicable Section 2 - Applicable Section 3 -

Not applicable. ANO will use only licensed packaging which has been designed under a QA program which has been submitted to the NRC for approval.

Section 4 - Applicable Section 5 -

Applicable Section 6 -

Applicable Section 7 - Applicable Section 8 -

Generally applicable except for paragraph 8.2.2 and 8.2.3. Due to size, uniqueness. Iow volume and the method of supplier identification of each package, ANO tagging of each package is not necessary.

Section 9 - Not applicable. We do not consider this subject as a "Special Process" in the context of 10CFR71, Appendix H Section 71.119 which is a restatement of 10CFR50, Appendix B Criterion 9.

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_ . _ .,_ . ._ _. -- _. - _ = _ . .

ATTACHMENT A (continued)

. 10CFR71 Appendix H Section 10 -

Applicable Section 11 -

Not applicable. ANO will not be testing the package in the context of 10CFR71, Appendix H Section 71.123 which is a restatement of 10CFR50, Appendix B Criterion 11.

Section 12 -

Generally applicable except for paragraph 12.3.4. This paragraph only applies to Radiation Protection and Radwaste measuring and testing equipment that is used to calibrate other desices (used as a standard).

Section 13 -

Generally applicable except for paragraph 13.5. ANO does not " store" packages, therefore the storage section does not apply.

Section 14 -

Not applicable. See Section 11 comments above.

Section 15 -

Generally applicable except for references to the various types of dispositions in paragraphs 15.2.3 to 15.2.5. Nonconforming material or equipment will be returned to >

the vendor or will be replaced.

Section 16 -

Applicable Section 17 -

Applicable l

Section 18 - Applicable

\

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. . ~ . - . - - - . .. . . . _ _ . . . ~ . . . . . , . . . - . - . . . - . . . . - . . - . = . - . . - . . . . . - - . . . . . . - - . - - - - - _ . . - . . -.

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PROGRAM TRANSPORT PACKAGES i

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I APPENDIX B l O

Q QUALITY PROGRAM FOR FIRE PROTECTION i

l

1.0 INTRODUCTION

l 1.1 The fire protection program was developed to define the organizational responsibilities, procedural controls, fire brigade stafling and training and the quality assurance provisions that have been established for the nuclear plant. The overall objective of the fire protection program i

is to minimize both the probability and consequences of postulated fires and to maintain the i

capability to safely shut down the plant if a fire should occur. l 1.2 The scope of the fire protection program includes those fire protection and detection systems, and those structures and components (such as fire doors, fire dampers, and penetration seals) i which, as identified in the plant's Fire Hazards Analysis Program Manual, are required to restrict the damage caused by a single exposure ' ire to safety-related equipment and equipment required to achieve and maintain safe plant shutdown to within those limits set forth in I Section 1 of Appendix R to 10CFR50.

1.3 The quality program for fire protection is designed to comply with the requirements of this manual and with the quality assurance guidelines identified in BTP-APCSB 9.5-1, Rev. 2, July 1981, Guidelines for Fire Protection for Nuclear Power Plants, subject to exceptions noted in this Appendix.

1.4 With respect to regulatory commitments, ANO is committed to implementing the requirements j of the following, subject to exceptions noted in this Appendix: i i

1. 10CFR50, Appendix A, General Design Criterion 3 - Fire Protection. j ENTERGY QA MANUAL OPERATIONS REV. 20 i p OPERATIONS ARKANSAS NUCLEAR ONE SECTION: APPENDIX B -QUALITY PAGE AB 1 PROGRAM FOR FIRE PROTECTION

~. _ ___ _ _ _ . . . - _ . _ _ _ _ _ _ . _ . _ _ _ _ . _ _ . _ _ _ . _ . _ _ _ .

2. Specific sections of 10CFR50.48, Fire Protection and 10CFR50, Appendix R. Fire Protection for Nuclear Power Facilities Operating Prior to January 1,1979. These (j sections are as follows:

Ill.G. Fire Protection Safe Shutdown Capability 11I.J. Emergency Lighting III.L. Alternative and Dedicated Shutdown Capability III.O. Oil Collection System for Reactor Coolant Pumps 1.5 Other fire protection commitments are contained in the following references and documents:

1. Facility Operating License (s)

2. Safety Analysis Reports (SAR)

3. Fire Protection Safety Evaluation Reports (SER) p l

4. Regulatory correspondence to and from the NRC (includes applicable NRC generic letters l and exemption letters for ANO).

1.6 The above requirements are implemented by controlling activities as described in this manual and Appendix and by procedures referenced in this manual and Appendix.

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2.0 ORGANIZATION (Q 2.1 The organizational structure and responsibilities of key personnel associated with the administration, implementation and evaluation of the fire protection program are described in Section 1.0 of this manual and as follows:

1. The Vice President, Operations ANO is the management position which has the overall responsibility for the development, implementation and assessment of the effectiveness of the fire protection program. He reports directly to the Entergy Operations Executive Vice President and Chief Operating Officer.

2. The General Manager, Plant Operations is responsible for the overall administration and implementation of plant operations and training in accordance with the fire protection program.

He reports directly to the Vice President, Operations ANO.

3. The Manager, Engineering Programs is responsible for the establishment and monitoring of fire prevention aspects of the program at the plant including control of combustibles, ignition sources and postings. The Manager, Engineering Programs reports directly to the Director, Design Engineering. The Manager, Engineering Programs is responsible for:

-Y ,

(1) Implementing, maintaining and assessing the fire prevention aspects of the program as defined in plant procedures (combustible controls, fire watches and fire drills)

(2) Developing inspection and surveillance criteria (3) Maintenance and revision of the Pre-Fire Plans

' 4. The Manager, Engineering Programs is responsible for monitoring and overviewing fire protection programs and design fire protection modifications. The Manager, Engineering ,

1 Programs reports directly to the Director, Design Engineering. Under his direction are l Fire Protection Engineers /Specialistfrechnicians who are responsible for:

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} ENTERGY QA MANUAL OPERATIONS REV. 20

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(1) Implementing, maintaining and assessing the fire protection aspects of the g program as defined in plant procedures (2) Performing fire protection evaluations (3) Providing guidance and technical support to the nuclear plant in the area of fire protection (4) Assuring that applicable regulatory requirements are included in the fire protection program (5) Assuring design reviews for fire protection modifications are performed I (6) Assuring that evaluations / assessments of the fire protection program are perfonned and results reported to management (7) Maintenance and resision of the Fire Hazards Analysis (FHA)

(8) Classification of F-list components for the Component Level F-list i

1 (9) Coordinating insurer, NRC and other fire protection inspections. j i

I (10) Assuring fire protection systems engineenng functions are performed (suppression, detection, barriers, fire pumps and water supplies).

5. The Director, Nuclear Safety is responsible for assuring that the fire protection program is implemented in accordance with the QA Manual Operations, SAR and applicable procedures. This is accomplished by the performance of audits and other prosisions of the QA Manual Operations. He shall assure that corrective action, when necessary, is taken. He reports directly to the Vice President, Operations ANO.

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6. The Director, Nuclear Safety is responsible for providing other responsible organizations with regulatory information and interpretations on regulatory issues related to fire protection. He is also responsible for providing interface with the NRC on fire protection matters, engineering evaluations and analysis of fire protection systems, as related to regulatory conunitments and control oflicense-based documents relating to fire protection. He reports directly to the Vice President, Operations ANO.

7. The Director, Design Engineering is responsible for assuring that the technical requirements specified in the Operating License, Safety Analysis Report, and other design basis documents, with respect to fire protection, have been satisfied in design modifications and design documents affecting ANO.

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3.0 OUALITY ASSURANCE PROGRAM A

3.1 This quality program is to ensure that the fire protection systems for safety-related areas (as defined in paragraph 1.2 of this Appendix) are controlled in accordance with applicable NRC regulations, industrial standards and codes, policies, rules, procedures and licensing documents. j The quality program is implemented through approved procedures. The effectiveness of the fire protection program is verified through surveillances and scheduled audits conducted by the Quality Organization, under the cognizance of the SRC. General requirements for this program are also described in subsections 2.4 through 2.7 of this manual, except that personnel performing inspections need not be certified to ANSI N45.2.6, when inspections are performed on equipment not listed on the Q-list.

3.2 Employees whose duties and responsibilities arc related to this fire protection program at or in support of the nuclear plant are to participate in appropriate training programs to assure that suitable proficiency is achieved and maintained in the work they are performing. I 3.3 Fire protection training for plant personnel is included as part ofindustrial safety in the General Employee Training Program. Personnel are periodically retrained in industrial safety in 1 accordance with approved procedures. Personnel assigned to the plant Fire Brigade are to

) receive additional indoctrination and training to assure their capability to fight fires is established and maintained. The Director, Training and Emergency Planning has the overall responsibility for these training programs.

4.0 DESIGN CONTROL 4.1 Section 3.0 of this manual is applicable for design control activities pertaining to the fire protection system.

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5.0 PROCUREMENT DOCUMENT CONTROL 5.1 The control.of procurement documents for fire protection-related materials, parts and components is described in Section 4.0 of this manual with the exception of paragraph 4.2.3, When these items are not associated with the Q-list, the procurement document is to include the requirement that items be U.L. listed or F.M. approved for fire protection use, where applicable, in accordance with approved procedures.

6.0 INSTRUCTION

S. PROCEDURE

S AND DRAWINGS 6.1 Inspections, tests, administrative controls, fire drills and training that govern the fire protection program are prescribed by documented instructions, procedures and drawings and are accomplished in accordance with these documents. Instructions, procedures and drawings are prepared, reviewed, approved and revised in accordance with approved procedures.

7.0 DOCUMENT CONTROL 7.1 Section 6.0 of this manual is applicable for the control of quality program documents related to fire protection.

I v

8.0 CONTROL OF PURCHASED MATERIAL. EOUIPMENT AND SERVICES 8.1 The control of purchased fire protection-related materials, equipment and senices is described in Section 7.0 of this manual. with the following exception related to subsections 7.2,7.3 and 7.5.

For the procurement of fire protection-related items or senices not associated with the Q-list, the vendor / contractor qualification esiteria (including periodic reassessment of their program) is not required. Nonconformances dispositioned repair or use-as-is by the vendor are to be submitted to and accepted by ANO only when so designated on the procurement document. i 1

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9.0 IDEM 1FICATION AND CONTROL OF MATERIALS. PARTS AND COMPONENTS

( 9.1 Section 8.0 of this manual is not applicable for the identification and control of materials, parts I

and components related to the fire protection system. No particular requirements for this section have been identified in BTP-APCSB 9.5-1, Rev. 2. The identification and control of materials, parts and components are conducted in accordance with existing procurement and materials management procedures and practices.

10.0 CONTROL OF SPECIAL PROCESSES l 10.1 Section 9.0 of this manual is not applicable for the control of special processes, as applicable to fire protection systems. No particular special process controls have been identified by BTP-APCSB 9.5 1, Rev. 2. The control of special processes for the maintenance of the fire protection system is performed in accordance with applicable approved procedures and practices.

1 A

11.0 INSPECTION  ;

11.1 Inspection activities applicable to the fire protection system are described in Section 10.0 of this  !

manual with the exception of paragraphs 10.2.2 and 10.3.2.3, when inspections are performed

$ (g on equipment not associated with the Q-list. The Regulatory Guides referenced in paragraph 10.2.2 are not applicable to the fire protection system. Individuals outside the Quality Organization who perform inspections only need to meet paragraphs 10.3.2 and 10.3.2.1.

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In addition to the provisions of this manual, inspections and surveillances are addressed in applicable portions of the SAR for each nuclear unit.

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12.0 TEST CONTROL 4

(, 12,1 A test program is to be established and implemented to ensure that testing is performed and verified on applicable systems and components to demonstrate conformance with design and system readiness requirements. The tests are to be performed in accordance with written test procedures and test results evaluated for conformance to the test objectives.

12.2 The control of testing activities is described in Section 11.0 of this manual. Surveillance testing requirements are identified in the Safety Analysis Report for each nuclear unit.

13.0 CONTROL OF MEASURING AND TEST EOUIPMENT 13.1 Section 12.0 of this manual is not applicable for the control of measuring and test equipment.

j No particular measuring and test equipment controls have been identified in BTP-APCSB 9.5-1, Rev. 2. Measuring and test equipment is controlled in accordance with applicable approved procedures and practices.

14.0 HANDLING STORAGE AND SHIPPING

( 14.1 Section 13.0 of this manual is not applicable for the handling, storage and shipping of fire protection-related materials and equipment. No particular requirements for this section have been identified in BTP-APCSB 9.5-1, Rev. 2. Handling, storage and shipping activities are controlled in accordance with applicable approved procedures and practices.

15.0 INSPECTION. TEST AND OPERATING STATUS 15.1 Measures are established to provide for the identification of items that have satisfactorily passed required inspections and tests and are documented per approved instructions or procedures.  !

15.2 Section 14.0 of this manual is applicable for identifying the inspection, test and operating status of the fire protection system.

ENTERGY QA MANUAL OPERATIONS REV. 20 j y OPERATIONS l t ARKANSAS NUCLEAR ONE SECTION: APPENDIX B -QUALITY PAGE AB-9 PROGRAM FOR FIRE PROTECTION

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16.0 NONCONFORhGNG MATERIAL, PARTS AND COMPONENTS f3 t 16.1 The control of nonconforming materials, parts and components related to the fire protection system is described in Section 15.0 of this manual, with the exception of subsection 15.3, when the item is not associated with the Q-list. Vendor nonconformances are to be submitted to ANO only when so designated on the procurement document.

17.0 CORRECTIVE ACTIONS 17,1 A corrective action system is established to ensure that conditions adverse to fire protection, such as failures, malfunctions, deficiencies, deviations, defective components, uncontrolled combustible materials and nonconformances, are promptly identified, reported and corrected.

17.2 Corrective action activities are controlled as described in Section 16.0 of this manual, with the following exception related to subsection 16.3. Vendors furnishing fire protection items not associated with the Q-list are not required to be listed on the QSL.

4 18.0 OUALITY ASSURANCE RECORDS i

{v 18.1 Records w hich furnish evidence that the criteria enumerated in this program are being met for activities affecting the fire protection program are to be prepared and maintained as described in Section 17.0 of this manual.

i 19.0 AUDITS l

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19.1 Audits are to be conducted and documented to verify compliance with the fire protection l program, including design and procurement documents, instructions, procedures and drawings and inspection and test activities. Section 18.0 of this manual is applicable for the control of audits related to the fire protection program.

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, PROGRAM FOR FIRE PROTECTION j

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19.2 As a minimum, the following audits of the fire protection program are to be scheduled at the j indicated frequencies:

a

,D i f)

a. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

b. An independent fire protection and loss prevention program inspection and audit shall be perfonned at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.

c. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

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$ APPENDIX C f STATION BLACKOUT

1.0 INTRODUCTION

1.1 The quality program for station blackout is designed to comply with the requirements of this manual and the quality assurance guidance identified in Appendix A of Regulatory Guide 1.155,

" Quality Assurance Guidance for Non-safety Systems and Equipment."

1.2 Attachment A to this Appendix identifies the applicability of each section of the Quality Assurance Manual Operations to the non-safety related systems and equipment used to meet trie ,

requirements of 10CFR50.63 and Regulatory Guide 1.155, August 1988. )

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'F ATTACHMENT A

{[ R.G.1.155 APPENDIX A l'

The following sections of the Quality Assurance Manual Operations are applied as described below

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' Section 1.0 - Applicable -

Section 2.0 Applicable ,

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( Section 3.0 Applicable '

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Section 4.0 - Requirements for the procurement of items and senices are to be clearly stated and documented to assure that applicable regulatory requirements, design bases, technical requirements and quality )

assurance criteria are included or referenced in procurement documents.

{- The preparation, review, approval and issuance of procurement i documents are to be in accordance with applicable procedures.

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Section 5.0 Applicable '

j, Section 6.0 Applicable  :

-1 Section 7.0 Applicable except for paragraphs 7.2,7.3 and 7.5 and the last i p sentence of paragraph 7.4.3 where verification of the vendor's certification program is not required.

Section 8.0 No particular requirements for this section have been identified in

R.G.1.155. The identification and control of materials, parts and  !

}' components are conducted in accordance with existing procurement . i 1' and materials management procedures and practices. l l Section 9.0 No particular requirements for this section have been identified in 4 R.G.1.155. The control of special processes which may impact station blackout systems and equipment are performed in

< accordance with applicable procedures and practices.

j' Section 10.0 Inspection activities generally applicable to station blackout systems

and equipment are described in section 10.0 with the exception of paragraphs 10.2.2 (Regulatoiy Guide applications) and 10.3.2.3.

Section 11.0 _ Applicable except for references to ASME B & PV Code.  ;

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' PROGRAM FOR STATION BLACKOUT i

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s Section 12.0 Ne particular requirements for measuring and test equipment

controls have been identified in R.G.1.155. However, measuring

4' and test equipment is controlled in accordance with applicable approved procedures and practices. -

I Section 13.0 No partic::!r r@irements for handling, storage and shipping are included in R.G.1.155. These activities are controlled in accordar.cc with applicable approved procedures and practices.

Section 14.0 Applicable i Section 15.0 Applicable except for paragraph 15.3 Section 16.0 Applicable except for paragraph 16.3 Section 17.0 Applicable Section 18.0 Applicable i

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